DRA Dragon Project - European University Institute

EUROPEAN UNIVERSITY INSTITUTE 

HISTORICAL ARCHIVES OF THE EUROPEAN UNION 

DEP 

DRA 

Dragon Project 

Florence 

Mars 2006

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© Historical Archives of the European Union 


2


Table of Contents 


DRA Dragon Project................................................................................................................ 4 

DRA.A Administration and Action ......................................................................................................5 

DRA.A-BM Board of Management.............................................................................................................5 

DRA.A-DPO Dragon Project Office............................................................................................................6 

DRA.A-FA Finances and Accounts............................................................................................................6 

DRA.A-FDWP Fuel Disposal Working Party..............................................................................................7 

DRA.A-GPC General Purpose Committee ................................................................................................7 

DRA.B Reports ..................................................................................................................................8 

DRA.B-AR Annual Reports ........................................................................................................................8 

DRA.B-DPR Dragon Project Reports.........................................................................................................9 

DRA.B-MPS Monthly Progress Statement ............................................................................................132 

DRA.B-OP Progress Reports.................................................................................................................133 

DRA.C Research & Development and Engineering.......................................................................135 

DRA.C-AD Assessment Documents......................................................................................................135 

DRA.C-FID Fuel Irradiation Dossier.......................................................................................................136 

DRA.C-ID Irradiation Documents...........................................................................................................137 

DRA.C-PAT Patent specifications..........................................................................................................140 

DRA.C-PS Project Specifications ..........................................................................................................141 

DRA.C-RDD Research and Development Division ...............................................................................142 

DRA.D Physics Meetings...............................................................................................................145 

3



DRA Dragon Project 

1959-1976 

13 linear metres 

306 files 

Commonly christened by ENEA the "Dragon Project", it was launched in 1959 at the Winfrith 

Heath nuclear research establishment of the United Kingdom, after the Steering Committee of 

Agency invited top level specialists in nuclear science and engineering from its Members and 

Associate countries and from EURATOM Commission to examine the most practical and fruitful 

methods of collaboration in the field of an experimental and prototype reactor. The main goal of 

the Dragon Project was the construction and the exploitation of an advanced type of hightemperature 

gas cooled reactor. 

4



DRA.A Administration and Action 

1959-1970 

Under this title were grouped the files produced by the admministrative bodies of the Dragon Project 

as well as other files which include information about the history of the project. 

DRA.A-BM Board of Management 

1959-1970 

6 files 

The Board of Management composed by a representative of each country involved on the 

project and one representing ENEA, was responsable for approving the programmes of 

work and annual budget. The Board was assisted by a General Purposes committee 

consisting of technical specialists representing also each country and ENEA. 

File: DRA-1 1959 

Minutes of Meetings 

Docs. coded BM(59)M.1 to 2 and BM(60)M.3 to 5. 

Old Record Code: 203/01/01203/01/02 


Working Papers 

Docs. coded BM(59)1 to 8 

Old Record Code: 203/01/03 

File: DRA-303 01/01/1967 - 31/12/1970 

Minutes of Meetings of the Board of Management 

Correspondance regarding the preparation and arrangement of the 25th, 26th and 

32nd meetings of the Board of Management. 

Old Record Code: 128772 



Minutes of the 12th meeting to the 24th meeting, including 

Draft budget 

Future of the Dragon Project 

Accounts 

Helium Purification Plant 

Irradiation of graphites in the dragon reactor in collaboration with general atomic 

Policy on the employment of project facilities for other organisations 

Project insurance 

Collaboration with USAEL 

Operation of the dragon reactor experiment 

Patents and liscencing policies 

Distribution of project information 



Minutes of the 27th meeting to the 35th meeting, including 

Annual reports 

Further extension of the Dragon Project 

Manufacture of coated particle fuel 

Dragon Agreement 

Report of the Working Party on the future programme and staff structure of the Dragon 

Programme 

5

Draft budget 

Helium Purification Plant 

UKAEA's legal liabilty on termination of project : Indemnity and Expenses 

Report on the GPC programme 

Carriage of nuclear matter : Shipping Indemnities 

Old Record Code: 128772 


Minutes of Special Meetings of the Board of Management 

Further extension of the Dragon Project 

Dragon Project 10th anniversary event 

Correspondance 

Old Record Code: 128777- 128780 



DRA.A-DPO Dragon Project Office 

1963-1971 

From this administrative unit of the Dragon Project, we found only two files concerning 

the history of the Project and documents related to its prolongation. 

Other documents from the Dragon Project Office can be found in the Fonds HB - 

Hendrik DeBruijn. 

File: DRA-300 1962 - 1971 

History of the Project 

Notes and Papers by C.A.Rennie, Chief executive of the Drogon Project, about the 

history and evolution of the Project. 

Language:ENGLISH 

Old Record Code: 202/01/02;222/03/03;222/01/03 


Extension of the Project 

Report by C.A.Rennie, Chief executive, titled "technical and Financial Aspects of an 

Extension of the Dragon Project Aggreement". 



DRA.A-FA Finances and Accounts 

1959-1974 

16 files 

Accounting documents. Reports from Commissioners to Accounts were sealed. Those 

seals for preservation motifs are kepted appart. Documents are mentioned "Dragon 

Project Use Only". Files are organised by year. 









6

























DRA.A-FDWP Fuel Disposal Working Party 

1974-1975 

Only one dossier was found from this body, andit includes agendas minutes and working 

papers. 


Fuel Disposal Working Party 

Meetings and reports regarding the disposal of irradiated fuel from the Dragon reator 

experiment 

DRA.A-GPC General Purpose Committee 

1959-1963 

The General Purposes Committe assists the Board of Management, specially in what 

concerns the eleboration of working programmes and approval of contracts. It was 

composed by specialists representing each of participating coutries and ENEA. 


7

Minutes of meetings 

GPC(59)M.1 to 3 

GPC(60)M.4 to 7 

GPC(61)M.9 to 10 



Working Papers 

GPC(59)1 to 14 (missing n.6) 





DPD Papers 

Papers coded DPD(59) to DPD(63), submited either to the Board of Manegment or to the 

General Purpose Committe. Includes an index of the papers organized by subjet. 

Includes also a subject index of the contracts. 


DRA.B Reports 

1959-1976 

There are several kinds of reports: Annual reports about the evolution of the project, progress reports 

from the Dragon Operations Group and Dragon Project Reports, a series that include either technical 

or administrative reports. 

DRA.B-AR Annual Reports 

1959 

Complete series of Annual Reports. 


01 



02 



03 



04 



05 



06 



8

07 



08 



09 



10 



11 



12 



13 



14 



15 



16 



17 




DRA.B-DPR Dragon Project Reports 

1960-1978 

The reports are of several types: 

- semi-anuual reports for the duration of the Project, summarising the work of the 

previous six months. Each has appendices listing the Project Reports to date as well as 

contractors' reports. There are also backlists of previous semi-annual reports by 

timespan. 

- technical reports on various aspects of the Project, its processes and results e.g.n. 964 

High Temperature Gas-Cooled Reactor Safety. N. 345 Fabrication of Spherical Carbide 

9



Particles. N. 448 Recent Results from the In-Pile Carbon Transport Loop. These often 

include material such as photographs, plans, graphs and tables. 

- reports on experiments carried out by Project Staff e.g. 346 Further Environmental 

Tests on Solenoid Operated Valves (...). N. 351 Experiments on the Irradiation of 

Graphite at High Temperatures. The contents are similar to those of the technical 

reports. 

Reports on the administrative aspects of the Project e.g. 362 Review of the Engineering 

Organisation during design and construction of the Dragon Reactor, or on associated 

work e.g. 368 Report on work at AERE for the Dragon Project. 

Reports were arranged by running numbers, 1 to 1000. These are allocated as they were 

issued and they are therefore arranged in chronological order but found by unique 

number. The last but one report in this sequence appears to be n. 981 (issued March 

1976). The final report summing up the entire Project and issued much later than the 

others, in November 1978, was n. 1000. 

Occasionally a number was not issued for any report. When this was the case it is noted 

by a phantom inserted at the relevant point. Other items appear to be simply missing, 

possibly from the time when these records were kept in the Project's own library at 

Winfrith in England. Occasionally there are two copies of one report. 

The reports seem to have been written in English. There are no French copies or 

translations. 

Typewritten booklets with cardboard covers (ususlly stapled unless the report was 

unusually long). Covers show subjet/title, report number, author(s), date of issue, 

permited circulation. If the report as presented as a paper at a seminar or conference 

this is also noted. Each report has a list of contents preceding the text. 


DPR 1 to 10 

Pages: 10 Reports 



Item: DRA-199.001 01/1960 

DPR 1 

Development of the design of the high temperature gas cooled reactor experiment 

(G.E. Lockett) 




DPR 2 

Dragon Programme Graphite Symposium (Dr. Hans Schmidt) 




DPR 3 

Das Projekt 'Dragon' und sein Reaktor Experiment (Hintermann, Shepherd, 

Lockett, Huddle) 




10



DPR 4 

Preliminary Safety Evaluation of the Dragon Reactor Experiment (Dickson, 

Schmidt) 




DPR 5 

Elastic Properties of Graphite (Bell, Hub, Smith) 




DPR 6 

Preliminary shielding report for the Dragon reactor experiment (Crawley) 




DPR 7 

On the possibilty of removing hydrogen from the Dragon coolant by diffusion 

through a palladium membrane (Horsley) 




DPR 8 

Some experiments on combined dust filter and restrictor units for the Dragon fuel 

element purge system (Horsley, Hosegood) 




DPR 9 

The distribution of fission products in the Dragon reactor experiment (Smidt, 

Fullom) 




DPR 10 

A programme for high temperature reactor kinetic calculations on the ferranti 

mercury computer (Blake, Crouch) 




DPR 11 to 20 




DPR 11 

High temperature heat transfer circular channel experiment introduction and rig 

calibration (Donne, Bowditch) 


11




DPR 12 

Problems associated with the penetration of noble gases through graphite (H. 

Schmidt) 



DPR 13 

The oxidation of solid fission products in the helium purge flow (E. Romberg) 



DPR 15 

The control of the Dragon reactor experiment at low power levels (J.P.H. Blake) 



DPR 16 

Bibliographic study of oxidation of carbon (Mrs. M.L. Pointub) 



DPR 17 

On the stability of flate plates under the influence of coolant flow (J. Schlosser) 



DPR 18 

An experimental investigation into the heat transfer characteristics of a delay 

bed using cross-flow cooling (H.F. Enzmann) 



DPR 19 

The power stabilty of reactors of Dragon type (J.P.H. Blake) 



DPR 20 

Fission product deposition in Dragon under normal operation (H. Schmidt, S. 

Fullom) 



DPR 21 to 30 

Pages: 10 files 



DPR 21 

The single channel low temperature heat transfer rig design, construction and 

commissioning (C.H. Robinson, K. Hansen) 


12




DPR 22 

Thermal conductivity measurement of Dragon type graphite. A survey of 

methods being used (H. Pass) 



DPR 23 

Leak testing of the test vessel and eperimental gaskets at Mannesman, 

Huckingen, West Germany (D. Barnes, F. Wade) 



DPR 24 

Preliminary report on dry bearings for the Dragon reactor experiment (H. Fricker) 



DPR 25 

Early work on thermocouples to measure graphite temperature of 800 C and 

higher (F.A. Reichardt) 



DPR 26 

Some aspects of the construction and sitting of gas-cooled reactors (C. Stelidler) 



DPR 27 

An appraisal of zirconium as a brazing medium for fuel boxes (R.C. Burnett, G. 

Marengo) 



DPR 28 

The leak-tightness of demountable flange assemblies using soft iron gaskets (N. 

Pollitt) 



DPR 29 

Fabrication of components for thorium doppler coefficient meaurements in the 

general atomic crital assembly (J.R.C Gough, G.B. Redding, R.C. Burnett) 



DPR 31 to 40 




DPR 31 

Papers and summary of discussion of meeting on post irradiation examination 

and radiochemical analysis 

13





DPR 32 

The measurement of prompt neutron lifetime by the perturbation technique 

theory and application to the zenith reactor (L.I. Tiren) 



DPR 33 

High temperature annulus rig experiment (R. Alami, A.A. Butcher) 



DPR 34 

Research and development division first semi-annual report (P.Marien) 



DPR 35 

A new method to measure the concentration of charcoal dust in an air stream 

(H.F. Enzmann) 



DPR 36 

The corrosion of mildsteel, stainless steel (18cr-8Ni-ITi) and inconel by iodine, 

tellurium, slenium and anatomy vapours (G.W. Horsley) 



DPR 37 

A direct heated graphite corrosion loop (R.T. Smyth, D.W. Sturge) 



DPR 38 

Radiographic inspection for Dragon fuel element graphite (H. Beutler, R.L. Grant) 



DPR 39 

An interactive solution of the reactor kinetic equations for the rod drop source 

jerk experiments (W. Hage, I.R. Cameron) 



DPR 40 

The development of low permeability graphite for the Dragon reactor experiment 

(L.W. Graham, W. Watt, W. Johnson, P.A.P Arragon) 



DPR 41 to 50 


14




DPR 41 

Some quantative remarks on leak rate measurements (G.C. Nullens) 



DPR 42 

Pressure drop in charcoal beds (H.F. Enzmann) 



DPR 43 

Concrete as a constructional material for the Dragon project (T.G. Williams) 




DPR 44 

Leak testing of the test vessel and experiment gaskets at Mannesmann, 




DPR 45 

Preparation of a capsule for irradiation in the Hawker Siddeley core replacement 

rig in Riso, Denmark (G.B. Redding, R.C. Burnett, H. Beutler, J.R.C. Gough) 



DPR 46 

The purification of helium in high temperature reactors (J.E. Antill, D. Bradley, 

R.H.Flowers, N. Hodge) 



DPR 47 

The manufacture and pore properties of a series of fine-grained graphites (T.R. 

Jenkins, B. Longstaff) 



DPR 48 

The adsorption of helium on coconut charcoal at -196 C and at pressures 

between 1 and 23 atmospheres (G.W. Horsley) 



DPR 49 

Preliminary report on stack wind tunnel tests (M.A Coudray, A. Bateman) 



DPR 50 

Heating experiement with bolt for the pressure vessel main flange (K. Hansen) 

15




DPR 51 to 60 





DPR 51 

The selection of greases for the lubrification of bearings in the Dragon reactor 

(G.W. Horsley, H. Fricker) 




DPR 52 

Methods of helium purification (E. Romberg) 




DPR 53 

Description of a one dimensional two group burn up programme for the mercury 

programme (J. Schlosser) 




DPR 54 

Approximate heat transfer and pressure drop characteristics of a Dragon 

channel (L.A. Husain) 




DPR 55 

Heat transfer analysis and early 'out of pile' test results on pluto loop 'A' (J.P.H 

Blake, R.A. Saunders) 




DPR 56 

Forming of a refractory spheroids by plasma jet and the development of a 

plasma furnace (D.W. Sturge, R.T. Smyth) 




DPR 57 

A three electrode plasma welding device for thermocouple hot junctions (R.T. 

Smyth, D.W. Sturge) 



16




DPR 58 

The variation of helium temperature in the Dragon reactor after loss of electricity 

supply (J.P.H. Blake) 




DPR 59 

Xenon reactivity variations in the Dragon Reactor after shutdown (J.P.H. Blake) 




DPR 60 

'Stewpot' A43 - Group code for calculation of neutron spectra and multi-group 

constants 

(L. Massimo, E. Schroder) 




DPR 61 to 70 





DPR 61 

Determination of the flux distribution produced by a source in an undercritical 

reactor (L. Massimo) 




DPR 62 

Skinner valve leak tests (Miss J.M.E. Kay) 




DPR 63 

Engineering aspects of the Dragon Reactor experiment (G.E. Lockett) 




DPR 64 

Permeability and pressure tests on the Dragon fuel box (H. Beutler, S. 

Mayerhofer, P. Good) 




DPR 65 

17



Post irradiation dissection and examination procedure for Riso core replacement 

rig capsule No.1 (P. Barr) 




DPR 66 

Leak testing of the test vessel and experimental gaskets at Mannesmann, 





DPR 67 

The use of molybdenum disilicide as a brazing medium for fuel boxes (R.C. 

Burnett, G. Marengo) 




DPR 68 

Code of practice for cleaning and corrosion protection of heat disposal and 

auxilliary circuits of the Dragon Reactor (J.F.G. Conde) 




DPR 69 

The present status of the system uranium-thorium-carbon (A. Houyvet) 




DPR 70 

The effect of a fine hole on the characteristics of the Dragon fuel box (S. 

Mayerhofer, H. Beutler, P.D. Good) 




DPR 71 to 80 





DPR 71 

Emissivity Report Part 1 - The development of aparatus and techniques for the 

measurement of spectral emissivities with some preliminary data nickel, nilo 40, 

and pyrista stainless steel (J.C. Stillwell) 




DPR 72 

Literature survey on carbon deposition from carbon monoxide (Mrs. F. Coen) 

18






DPR 73 

Reaction of 'conventional' Dragon fuel inserts in the heat treated condition with 

moisure (G. Marengo) 




DPR 74 

A one dimensional analytical six group critical programme (O. Kalnaes, L. 

Massimo) 




DPR 75 

Research and development division second semi-annual report 1 January - 30 

June 1961 (P. Marien) 




DPR 76 

Research and development aspects of the Dragon Reactor Experiment (L.R. 

Shepherd, P.J. Marien) 




DPR 77 

Errors introduced into thermocouple systems by unexpected signals from 

insulating materials (J. Kingdom) 




DPR 78 

Some tests on P.T.F.E. valve seats (C. Harper, J.W. Humphries, L.A. Husain) 




DPR 79 

Progress in the chemistry and chemical enginerring branch of the research and 

development division (H. deBruijn) 




DPR 80 

The metallurgical properties of the Dragon Reactor pressure vessel (J.F.G. Conde) 



19


DPR 81 to 90 







DPR 81 

The influence of fuel box permeability on fission product heating in the Dragon 

purge stream and fission product plant (D.B. Crawley) 




DPR 82 

Calculations on the zenith reactor (O. Kalnaes) 




DPR 83 

Chemistry and chemical engineering applied in high temperature gas cooled 

nuclear power reactor (H. deBruijn) 




DPR 84 

The measurement of high temperatures by the determination of the velocity of 

sound waves in materials (E.A Thorne, E.G.H. Mobsby) 




DPR 85 

Adsorption errors in the sampling of gases (E.H. Voice) 




DPR 86 

A robust flowmeter for the measurement of very flows (L.A. Husain, C.H. 

Robinson) 




DPR 87 

Project Dragon (P.Marien) 




DPR 88 

20



Local heat transfer and average friction coefficients for subsonic laminar, 

transitional and turbulent flow of air in a tube at high temperature (M. Dalle 

Donne, F.H. Bowditch) 




DPR 89 

Experiments on seperation procedure for krypton and xenon in connection with 

pluto loop radiochemical sampling (H. Lengweiler) 




DPR 90 

Tests on absorbe rods control mecanism (P. Nectoux, J.R. Last) 




DPR 91 to 100 





DPR 91 

A preliminary estimate of the physical consequences of using coated particle fuel 

inserts in the Dragon Reactor experiment (L.A. Husain) 




DPR 92 

Research and development division third semi-annual report 1July - 31 

December 1961 (P. Marien) 




DPR 93 

Fuel element development - fission product emitting fuel (J.R.C. Gough) 




DPR 94 

The containment of high temperature reactors (H.W. Schmidt, S. Allen) 




DPR 95 

Some metallurgical properties of the Dragon Reactor pressure vessel (J.F.G. 

Conde) 


21





DPR 96 

The water flow visualisation rig results obtained on the reactor channel (K. 

Hansen) 




DPR 97 

Dimensional behaviour of 'conventional' Dragon fuel inserts (G.B. Redding) 




DPR 98 

Emissivity Report Part 2 - Measurement of spectral emissivity of EXY 60 graphite 

(J.C. Stillwell) 




DPR 99 

The irradiation programme of the Dragon high temperature reactor project (R.A. 

Saunders) 




DPR 100 

Report of working party of Board of Management on an extension of Dragon 

Project Agreement (Members of the Working Party) 




DPR 101 to 110 





DPR 101 

The Compatability of Some Gasket Materials with Mild Steel at 300 Centigrade 

(AG. A1) and Stainless Steel at 450 Centigrade (G.W. Horsley, B.H. Hedman) 




DPR 102 

The Boiling of Liquidation Nitrogen in Cylindrical Vessels (E. H. Voice). 



22



DPR 103 

The Corrosion of Graphite in Dragon and the Deletion of Reactants (L. Valette). 




DPR 104 

Coolant Processing in the Dragon Project (F. C. Wood). 




DPR 105 

Fission Product Technology of High Temperature Reactors (E. Glueckauf). 




DPR 106 

Skinner Valve Leak Tests (Miss J. M. E. Kay, R. C. Hollick). 





DPR 107 

The Purification of Graphite by Treatment with Halogens at Temperatures up to 

1000 C (G. W. Horsley). 




DPR 108 

Oxydation of Graphite with Oxygen between 1000 C and 2000 C (J. E. M. 

Nagle). 




DPR 109 

A Low-level Mesurement of Kr85 (E. H. Voice). 




DPR 110 

Temperatures in Dragon : a Programme for the Ferranti Mercury Computer (C. 

Zanantoni). 




DPR 111 to 120 

Pages: 9 reports 



23



DPR 111 

Diffusion of Gases in Graphite Pares (Truitt, Evans, Mason). 




DPR 112 

Effect of Un-pare Diffusion on Graphite Corrusion Rate (E. Wicke). 





DPR 113 

Estimate of Film Boiling Safety Margin in Dragon Primary Heat Exchanger (L. A. 

Husain). 




DPR 114 

The Role of Irradiation Experiments in a Reactor Development Programme (L. R. 

Shepherd). 




DPR 115 

Research and Development Division Fourth Semi-annual Report (1st January - 

30 June 1962) (P. Marien). 




DPR 117 

Contribution to the Study of Carbon Oxydation (F. M. Lang). 




DPR 118 

Tests on Stage 1 of the 37-Way Selector Valve Prototype (G. C. Nullens, M. Day, 

B. Aarset). 




DPR 119 

An Apparatus for Measuring the Young's Modulus of Full Size Dragon Graphite 

Fuel Tubes Using a Non-destructive Method (T. B. Thomsen). 




24



DPR 120 

Testing of Pyroltytic Carbon Coated Fuel Particles Development Programme (S. 

Nybo, C. Vivante). 




DPR 121 to 130 




DPR 121 

Preliminary Report on the Safety Aspects of Pressure Relief of the Secondary 

Circuit in the Heat Disposal System (M. A. Coudray). 



DPR 122 

Absorber Rod Control Circuit (L. Caldarola, G. Dondi, J. R. Dean). 



DPR 124 

Das Warmeabfuhrsystem des OECD - Hochtemperatur Reaktors Dragon (H. W. 

Müllek). 



DPR 125 

A Power Connector for the Graphite Heaters in the Seven Element Experiment (J. 

Kingdon). 



DPR 126 

The Dragon Freezer - A Theoretical Investigation of the Heat Transfer 

performance (L. A. Husain). 



DPR 127 

The Preparation of High Density Graphite Using Carbon Brack (P. Cornault). 



DPR 128 

The Dragon Project Engineering Programme (G. Franco). 



DPR 129 

Some Engineering Problems Associated with the Dragon Reactor Experiment (G. 

Coast). 


25




DPR 130 

The Corrosion of Graphite in an H. T. G. R. (M. L. Pointub, L. Valette, H. de 

Bruijn). 



DPR 131 to 140 




DPR 131 

The Irradiation Programme-review of Results (P. Barr, R. A. Saliders). 



DPR 132 

Phase Equilibrium and Thermodynamic Studies of Carbide Systems Related to 

High Temperature Reactors (F. Benesovsky, E. Rudy). 



DPR 133 

A Basic Study of the Thorium-Uranium-Carbon System (M. Marchal, A. Accary, 

C. E. A. Saclay). 



DPR 134 

Development Work on Carbide Fuel Particles (Bildstein, Koss, Rudy). 



DPR 135 

The Civil H. T. R. Reference Design Study (Design Office). 



DPR 136 

Post-irradiation Radiochemical Analytical Studies on Dragon Wops at A. E. R. E., 

Harwell, dec. 1962 (P. E. Brown, R. H. Flowers, D. F. M. Lupton). 



DPR 137 

Some Measurements of the Diffusion of U-235 Fission Products and Pa-233 from 

"coated" Fuels, dec. 1962 (Flowers, Pattison, Pummery, Watts). 



DPR 138 

Evaluation Studies on Coated Particles at S. G. A. E, Seibersdorf (Koss, 

Bildstein, Proksch). 

26





DPR 139 

Studies on Coated Particle Fuel Involving Coating Consolidation and Evaluation. 



DPR 140 

Development of Production Scale Procedures for Coating Fuel Particles (Rudy et 

al). 



DPR 141 to 150 





DPR 141 

The design of the Dragon first charge fuel elements (E. Smith) 




DPR 142 

Tentative Proposals for the Quality Control, Inspection and Testing of Production 

Fuel Elements for the Dragon Reactor Experiment (J.F.G. Conde) 




DPR 143 

Applications of X-Ray Microanalysis and X-Ray Projection Microradiography to 

the Study of High Temperature Fuels (R. Theisen et al) 




DPR 144 

Progress Report on H.T.G.C. Pluto Loop Irradiations II and III (Lengweiler, F. 

Sterry) 




DPR 145 

Design Principals for Control Mechanisms (Dean, Caldarola) 




DPR 146 

The Fuel Element Graphite (L.W. Graham, M.S.T. Price) 

27




Item: DRA-213.147 1963 

DPR 147 

Forming of Refractory Spheroids Part II (D.W. Sturge, R.T. Smyth) 





DPR 148 

The Development of the Plasma Arc Furnace for Fuel Melting (T.A.J. Jaques, D.W. 

Sturge) 




DPR 149 

Fabrication of Spheroidized Particles by the Power Metallurgy Agglomeration 

Process (F. Gorle, E. Jonckheere, J. Vangeel) 




DPR 150 

The Fuel Element Programme (R.A.U. Hudde) 




DPR 151 to 160 





DPR 151 

Development of a Coated Particle Fuel (R.C. Burnett, L. Bisdorff, J.R.C. Gough) 




DPR 153 

Evaluation Studies of Coated Particles Fuel within the Project (C. Vivante, G. 

Hauser, S. Nybo) 




DPR 154 

Leak Testing the Dragon Reactor Pressure Vessel (D. Barnes, F. Wade) 




28



DPR 155 

Representation of the Neutron Spectrum by an Analytical Expression and its 

Application (H. Brunender) 




DPR 156 

A Comparison of Codes for Spectrum and Reactivity Calculations (L. Massimo, B. 

Micheelsen) 




DPR 157 

Temperature Measurement in the Dragon Reactor (F.A. Reichardt) 




DPR 158 

The Present Position of Reactor Kinetic Studies on the Dragon Reactor 

Experiment (J.P.H. Blake) 




DPR 159 

The Significance of the Buckling for the Spectrum and the Group Cross Sections 

(B. Micheelsen) 




DPR 160 

Testing on Teddington Valves (H.J. Woodley) 




DPR 161 to 170 





DPR 161 

A Preparation of Graphite with a Narrow Spectrum of Fine Pores (J. Bentolila) 




DPR 162 

The Design and Operation of the Core Unclamp Mechanism of the Dragon 

Reactor (J.D. Hart) 


29




DPR 163 

Bearings and Gears for Operations in Inert Cases (H.W. Fricker) 





DPR 164 

Study of the Influence of Particle Size Distribution on the Pore Spectrum of Fine 

Grain Graphites (J. Bentolila) 




DPR 165 

Research and Development Division Fifth Semi-Annual Report (P. Marien) 




DPR 166 

Physics Experiments on the Dragon Reactor Experiment (J.P.H. Blake, V.E. Della 

Loggia, J. Reber) 




DPR 167 

Tests and Data Concerning Platinel, a New High Temperature Thermocouple (M. 

Dalle Donne) 




DPR 168 

Equipment for the Reactor Physics Experimental Programme in the Dragon 

Reactor (V.E. Della Loggia) 




DPR 169 

An Appartus to Measure the Effects of Irradiation on the Thermal Conductivity of 

Dragon Type Fuel Tubes (H. Pass) 




DPR 170 

Proposals for Transfer Function Measurements on the Dragon Reactor 

Experiment (J. Reber) 



30


DPR 171 to 180 






DPR 171 

Simplified Calculations of Different Dragon Power Transfer Functions (W. Hage) 





DPR 172 

'MUPO' An IBM-7090 Programme to Calculate Neutron Spectra ans Multi-Group 

Constants (J. Schlosser) 




DPR 173 

Burn-up Assesments for a Land Based Power Reactor (G. Beliaev, H. Bruneder) 




DPR 174 

Dragon Reactor Automatic Control (L. Caldarola) 




DPR 175 

Progress in Shielding Design in the Dragon Project (D.B. Crawley) 




DPR 176 

Lifetime Optimisation of a Core Suitable for Long Term Irradiation Experiments 

(L. Massimo) 




DPR 177 

The First Loading of the Dragon Reactor Experiment (E. Schroder) 




DPR 178 

Control Rod Calculations for the Dragon Reactor Experiment (J. Blomstrand) 



31



DPR 179 

Power Distribution and Core Temperatures in the Dragon Reactor Experiment 

(J. Blomstrand) 





DPR 180 

Thorium Resonance Absorption in the Fuel Elements of the Dragon Reactor 

Experiment 

(E. Schroder) 




DPR 181 to 190 





DPR 181 

New Calculations on the Second Loading of the Zenith Reactor (B. Micheelsen) 




DPR 182 

Thermal Conductivities of Some High Temperature Materials (H. Pass, J.C. 

Stillwell) 




DPR 183 

A Review of the Activities of the Dragon Heat Transfer and Gas Dynamics Group 

(L.A. Husain) 




DPR 184 

Experiemtal Local Heat Transfer and Friction Coefficients for Sub-sonic Laminar 

Transitional and Tubulent Flow of Air or Helium in a Tube at High Temperatures 

(M. Dalle Donne, F.W. Bowditch) 




DPR 185 

High Temperature Convective Heat Transfer in an Annulus (R. Alami, A.A. 

Butcher) 



32




DPR 186 

The Effect of Geometry on Convective Heat Transfer in the Dragon Channel (C.H. 

Robinson, K. Hansen) 




DPR 187 

Thermal Emissivity of Some High Temperature Materials (J.C. Stillwell) 




DPR 188 

Experiments on Leak Rate and Back Diffision Characteristics of the Fuel Element 

(P.D. Good) 




DPR 189 

The Feasability of Using Molecular Sieve 4A Pellets for the Removal of CO2 and 

H2O - Vapour from an H.T.G.R. Purge (By E. Romberg) 




DPR 190 

Reactor Physics and Heat Transfer Work in the Dragon Project (K.O. Hintermann) 




DPR 191 to 200 





DPR 191 

A Nozzle Themocouple for Measurements in High Temperature Gases (M. Dalle- 

Donne, F.H. Bowditch) 




DPR 192 

Comparative Evaluation of Temperature Distribution (R. Alami) 




DPR 193 

33


Desorption of Water (H. Tjericstra, L. Werner) 





DPR 194 

A Non-destructive Method for the Determination of the Uranium and Thorium 

Content of Powders, Coated Fuel Particles and Fuel Cartridges (P. Barr, R. 

Pointud) 




DPR 195 

Experimental Work Carried Out on Dragon Heat Exchanges Test Flange 

Assembly 

(H.J. Woodley) 




DPR 196 

Proceedings of the Dragon Project Fuel Element Symposium Held in 

Bournemouth 28-29 January 1963 




DPR 197 

Flanged Joints for Dragon Primary Circuit - Preliminary Report (W.E. Simmons) 




DPR 198 

Electron Beam Welding Experiment for Bursting Disc Assemblies (R. Hansen) 




DPR 199 

Pressure Drop Characteristics of the Seven Element Rig (R. Alami) 




DPR 200 

Survey of Important Design Parameters for the Dragon Heat Disposal Circuits 

(C.H. Tweedy) 




DPR 201 to 210 



34





DPR 201 

Helium Leak Testing Techniques : Containment of Helium Escaping from Leaks 

by Polythene Sheets (J. Milne, A.D. Hammond) 




DPR 202 

Experimental Measurements of Some of the Properties of Irradiated and 

Unirradiated Elastomers (G.C. Nullens) 




DPR 203 

'Mafia' - A One-dimensional Burn-up Code (L. Massimo, J. Schlosser) 




DPR 204 

Preconcentration of Impurities in the Dragon Purge Flow by Thermal Diffusion (J. 

Los, C.A. Velds, E. Romberg) 




DPR 205 

Kinetic Measurements of the Reaction of Carbon with Carbon Dioxide in a 

Differential Reactor 

(K. Hedded, A. Lowe) 




DPR 206 

Leakage and Stiffness Measurements Made on a Manhole Flange and Cover 

Test Assembly (H.J. Woodley) 




DPR 207 

Radiochmical Analysis of Fission Products in the Dragon Reactor (P. Acciarri, E.J. 

Mitchell) 




DPR 208 

The Choice of Gas Bearing Materials (H.W. Fricker) 



35




DPR 209 

The Correlation Between Pore Size and Distribution, Permeability and Diffusion 

in Graphite (J. Schlosser) 




DPR 210 

Multiplication Factor Definitions Theory and Experiment (B. Micheelsen) 




DPR 211 to 220 





DPR 211 

Burn-up in a Large High Temperature Gas Cooled Reactor (J.Schlosser) 




DPR 212 

Production Scale Development of Fuel Cartridge Consolidation (G.B. Redding) 




DPR 213 

A Study on the Trapping of Iodine at High Temperatures on Activated Charcoal 

(R.O Lingjearde, L. Podo) 




DPR 214 

Preparation and Evaluation of Fission Product Retaining Fuel for the III Charge of 

the Pluto Loop (J.R.C Gough et al) 




DPR 215 

The Application of X-Ray Projection Microscopy to the Quality Control and 

Inspection of Coated Particle Fuels for the Dragon Reactor Experiment (J.F.G. 

Conde) 




36



DPR 216 

The Design and Operation of the Inner Reflector of the Dragon Reactor (J.D. Hart) 




DPR 217 

Design Features and Test Results of the Main Circulators for the Dragon Reactor 

(Brown Boveri) 




DPR 218 

Remote Controlled Viewing for the Dragon Reactor Main Pressure Vessel (D.S. 

Ritchie) 




DPR 219 

The Steel and Concrete Containment Buildings for the Dragon Reactor (N.T. 

Barrett) 




DPR 220 

The Installed Leak Detection System of the Dragon Reactor Experiment (H.F. 

Enzmann) 




DPR 221 to 230 





DPR 221 

Electrical Aspects of the Dragon Reactor (T.J. Glover) 




DPR 222 

Experimental Work on Gaseous and Boiling Heat Transfer Associated with the 

Design of the Dragon Primary Heat Exchangers and Some Aspects of their 

Manufacture (P.V. Gilli) 




DPR 223 

Secondary Circuit Quench Tanks for the Dragon Reactor (Borsig A.G.) 

37





DPR 224 

Hysteresis Clutch Drive Units (D.G. Young) 




DPR 225 

Dragon Project Helium Leak Testing (F. Wade) 




DPR 226 

Erection of Reactor Primary Circuit (J. Pugh) 




DPR 227 

The Irradiation Behaviour of Coated Particle Fuel (J.B. Sayers et al) 




DPR 228 

The Fisison Product Delay Beds for the Dragon Reactor Experiment (S.E.C.A.) 




DPR 229 

The Primary Circuit Gas Bearing Circulators for the Dragon Reactor Experiment 




DPR 230 

The Charge/Discharge Machine for the Dragon Reactor Experiment (S.E.C.A.) 




DPR 231 to 240 





DPR 231 

Reactor Control and Instrumentation (C. Watts) 



38




DPR 232 

Thermocouple Connector Life Test (S.J. Willshire, R.C. Hollick) 





DPR 233 

Behaviour of Coated Particles Subjected to Acid Leaching and Thermal Shock 

Tests (P.D Good, R. Pointub) 




DPR 234 

Dry Friction in Gas Bearings and Shaft Seals (H.W. Fricker) 




DPR 235 

Research and Development Division Sixth Semi Annual Report (P.Marien) 




DPR 236 

Blowers and Variable Frequency Generating Sets Control Circuit (G. Dondi, P.G. 

Giordano) 




DPR 237 

Temperature Measurement in the Reactor Pit (P.G. Giordano) 




DPR 238 

Control Circuit for the By-pass Valves in the Primary Gas Circuit (L. Caldarola, 

P.G. Giordano) 




DPR 239 

Primary Gas Circuit Instrumentation (P.G. Giordano) 




DPR 240 

39


The Role of Gas Bearing Circulators in the Dragon Reactor (W.F. Shilling) 




DPR 241 to 250 





DPR 241 

Analysis of Trace Impurities in Helium (T.B. Christensen, E. Romberg) 




DPR 242 

Safety Assesment for Dragon Fuel Element Production (M.S.T. Price) 





DPR 243 

The Power Metallurgy Agglomeration Method for Fabrication of Carbide Spherical 

Particles (F. Gorle, J.J. Huet) 




DPR 244 

Loop Irradiations and Radiochemical Examination of Irradiated Fuel Components 

at Studsvik (L. Hammer, P. Svensson) 




DPR 245 

Tests on Stage II of the 37-Way Selector Valve Prototype (H.J. Woodley) 




DPR 246 

Electron Beam Welding Experiments for High Temperature Thermocouple 

Sheaths (R.A. Hansen) 




DPR 247 

Electron Beam Welding Experiments for Bursting Disc Assemblies (R. Hansen) 



40



DPR 248 

The Leak Testing of the Helium Purification Pilot Plant (J.M. Milne) 




DPR 249 

Proceedings of Dragon Project Physics Symposium 7 - 9 May 1963 




DPR 250 

Development Works on Simple Valves (H.J. Woodley) 




DPR 251 to 260 





DPR 251 

Development work on Seals (H.J. Woodley) 





DPR 252 

Determination of Primary Circuit Behaviour in the Dragon Reactor by the use of a 

Nomogram (J.P.H. Blake) 




DPR 253 

Gas Chromatography and its Application to Gas Analysis for the Detection of 

Traces (C.H. Lambert) 



Item: DRA-224.254 

DPR 254 

Final Report on Radiation Damage in Graphite (CON/WIN/51099) (P. Sublet) 




DPR 255 

1250 MW (TH) H.T.G.R. Preliminary Design Study (CON/WIN/52319) Final 

Report 



41



DPR 256 

The Dragon High Temperature Multi-Purpose Laboratory Furnace (R. Hansen) 





DPR 257 

The Gas Sampling Analysis System fo the Dragon Reactor Experiment (H.F. 

Enzmann) 




DPR 258 

Removal of Fission Product Noble Gases from the Helium of a High Temperature 

Gas Cooled Reactor Using Charcoal at Low Temperature (H. deBruijn) 




DPR 259 

Determination of the Optimum Combination of Valve Component Geometry and 

Materials (G.C. Nullens) 




DPR 260 

Physical Methods of Determining Isotopic Contents of Irradiated Fuel Specimen 

(F.P. Viehbock) 




DPR 261 to 270 





DPR 261 

The New Cross Section Library of the Dragon Project (U. Nyffenegger, J. 

Schlosser). 




DPR 262 

Studies on the Coating of Fuel Particules for the Dragon Reactor Experiment (D. 

Kern, J. R. C. Gough, H. Beutler). 



42




DPR 263 

Development of Fuel Element Assembly Techniques for the First Charge of the 

Dragon Reactor Experiment (R. C. Burnet, J. R. C Cough, R. P. Sinden). 




DPR 264 

Chemical Analysis of Fuel Particules (R. Kingsjaeder, L. Podo). 




DPR 265 

Plutonium Fuel Cycles in High Temperature Gas Cooled Reactors. 




DPR 266 

Temperature Distributions in Laboratory Scale Coating Furnaces (D. Kern, J. R. C 

Gough). 




DPR 267 

Loading Calculations for the Dragon Reactor Experiment (H. Gutmann, B. 

Micheelsen, G. Preinreich) 




DPR 268 

The Design and Manufacture of the Thermal Column (E. Smith). 




DPR 269 

Reactor Test Vessel and Test Programme (J. Puch). 




DPR 270 

Development of Physical Methods of Fuel Analysis. Annual Technical Report. 

Feb.63 - Jan 64. 




DPR 271 to 280 



43




DPR 271 

The Dragon Helium Purification Pilot Plant (E. H. Voice, F. C. Wood). 




DPR 272 

The Dragon Helium Purification Pilot Plant (E. H. Voice). 




DPR 273 

Sinterability of Thorium-Uranium Dicarbide Fuel Kernels (L. Bisdorff). 





DPR 274 

Work on the Dragon Fuel at RAE Farnborough since Jan.'63 (R. H. Bickerdike, M. 

C. Ranson, G. Hughes). 




DPR 275 

A Simple Vacumm-insulated Cline and its Performance (E. H. Voice). 




DPR 276 

The Effect of Moisture on the Adsorption of Kripton on Charcoal (E. Romberg). 




DPR 277 

Electron Bean Soldering Experiments for Brushing Disc Assemblies (R. A. 

Hansen). 




DPR 278 

The Steady State Diffusion of Fission Product Metals in Pyrocarbon (E. Groos). 




DPR 279 

44



A Brief Description of Metallographic Laboratory Practice in the Dragon Project (J. 

F. G. Condé, P. Keegan). 




DPR 280 

Seventh Annual Report for the Period 1 July 63 - 31 Dec 63 (P. Kaul). 




DPR 281 to 290 





DPR 281 

The Dragon Dummy Fuel Elements (E. Smith). 




DPR 282 

Study of Performance of Tertiary Circuit Control Valve (W. S. A. Black, J. 

Holzner). 




DPR 283 

Safety Submission for the Zero Energy Phrase of Operation of the Dragon 

Reactor Experiment (A. N. Dickson). 




DPR 284 

Thermal and Electrical Conductivities of Dragon Fuel Cartridges (J. M. Milnc). 




DPR 285 

The Properties of a Vertical Hersch Cell (P. D. Capp, P. S. Gray, W. J. Symons). 




DPR 286 

TThorium Uranium Fuel Cycles in Large H. T. G. R. (J. Schlosser). 



45




DPR 287 

The Problem of Weld Craching in Machine Welds in Austenitic Stainless Steel 

Valves (J. F. G. Condé). 




DPR 288 

Detection and Location of Faculty Fuel Elements in the Dragon Reactor (P. 

Acciarri, E. S. Mitchell). 




DPR 289 

The Physics Commissioning Programme for the Dragon Reactor Experiment (J. P. 

H. Blake). 




DPR 290 

Dynamic Behavious of Gaseous Fission Products in Charcoal Adsorber Columns 

(L. Werner). 




DPR 291 to 300 





DPR 291 

The Development of Fuel and Care Materials for High Temperature Power 

Reactors (L. W. Graman, R. A. Saliders) 




DPR 292 

The development of the Production Process for the Fabrication of the 

Zirconium/Uranium Monocarbide Fuel Kernels for the First Charge of the Dragon 

Reactor (G. W. Horsley, L. J. Hanicart). 




DPR 293 

Preliminary Study of the Grind-Leach Head-end Treatment of Coated Particule 

Fuel (R. O. Ungjaerde, P. Lodo). 



46



DPR 294 

Pitting Corrosion in Dragon Reactor Graphites (N. Pollitt). 




DPR 295 

Testing and Evaluation of Reactor Fuel Particules (P. Icoss, H. Bildstein). 




DPR 296 

Final Shielding Report for the Dragon Reactor Experiment (D. B. Crawley). 





DPR 297 

Semi Annual Report on Research into the Sol-gel Process of Preparing Carbide 

Fuel Particules 1 Jan. - July 64 (M. E. Hermans, Plas). 




DPR 298 

Steam Leak Detection in the Secondary Circuit of the Dragon Reactor (E. Davis). 




DPR 299 

Control Scheme for Rateau Browers. 




DPR 300 

The Physical and Mecanical Properties of Dragon-Pechiney G5 Graphite (G. 

Kamoun, M. Gateau). 




DPR 302 to 310 


Language:ENGLISH;FRENCH 



DPR 302 

A Comparison of the Power Casting and Hot Pressing Routes for the Preparation 

of Dragon Fuel Inserts (D.W. Savage, G.B. Redding, G. Williams) 



47




DPR 303 

Etudes sous Irradiations de Combustible Etanches Destines au Reacteur Dragon 

(G. Hauser) 

Language:FRENCH 



DPR 304 

Impregnation of Graphite Specimens Using the Furfurly Alcoholic Impregnation 

Process 

(R.A. Martina, O.J. Vohler) 




DPR 305 

Tests on Soleroid Operation Valves for Leak Detection and Gas Sampling 

Systems 

(H.J. Woodley) 




DPR 306 

Experimental Study of Tilting Pad Gas Bearings (C. Mech, J. Poulain, H.W. 

Fricker) 




DPR 307 

Preliminary Proposals for Post-irradiation Examination of Fuel Elements from 

Dragon Reactor Experiment (R.A. Saunders) 




DPR 308 

The Retention of Fission Products in Dispersed Fuels (F.P.O. Ashworth) 




DPR 309 

Helios, a Zero-dimensional Multi-group Burn-up Programme (J. Schlosser) 




DPR 310 

Eight Semi-annual Report, 1 January - 10 June 1964 (P. Kaul 



48


DPR 311 to 320 







DPR 311 

Safety of Operations in the Manufacture of Driver Fuel for the First Charge of the 

Dragon Reactor and Modifications to the Safety Document for the Dragon Fuel 

Element Production Building (H. Beutler et al) 




DPR 312 

The Programme of Irradiation Damage and Corrosion Monitoring for the Pressure 

Vessel and Internal Structure of the Dragon Reactor (J.F.G. Conde) 




DPR 313 

Experiments of Gas Bearings for the Dragon Primary Circulators (Cyril H. 

Robinson) 




DPR 314 

The Emergency Circuit of the Heat Disposal System (W.S.A Black, J. Holzner) 




DPR 315 

Diffusion in Coated Particle Fuel (J. Fally, C.E.A. Saclay) 




DPR 316 

Review of Irradiation Results of Dragon Coated Particle Fuel (J.H. Coobs, G.P. 

Hauser, C. Vivante) 




DPR 317 

Microphotographic Examinatiobn of the First Stages of Carbon Deposition from 

Carbon Monoxide on Iron Surfaces (J. Hennault et al) 




DPR 318 

49


Fabrication of Spherical Carbide Particles (J.J Huet) 





DPR 319 

Rate Constraints of the Reaction of Carbon with Carbon Dioxide (K. Hedden, A. 

Lowe) 




DPR 320 

X-ray Microprobe Studies of Irradiated Fuel Particles (D. Quartaert, H.W. 

Schleicher) 




DPR 321 to 330 





DPR 321 

The Developments of the Production Process for the Thorium/Uranium Dicarbide 

Fuel Kernals for the First Charge of the Dragon Reactor (R.C. Burnett, L.J. 

Hankark, A.W. Horsley) 




DPR 323 

Design Safety Report of the Dragon Reactor Experiment (A.N. Dickso) 




DPR 324 

Determination of Fission Product Activities in Graphite by Gamma Spectrometry 

(H. Paul, J.H. Blomstrand) 




DPR 325 

Report on Work at A.E.R.E from the Dragon Project, May - October 1964 




DPR 326 

The Application of Non-destructive Techniques in the Quality Control Inspection 

and Testing of Fuel Materials for the Dragon Reactor Experiment (J.F.G Conde et 

al) 

50






DPR 327 

The Quality Control, Inspection and Testing of Fuel Materials for the First Charge 

of the Dragon Reactor Experiment (Conde et al) 




DPR 328 

A Summary of the Results Obtained in Quality Control, Inspection and Testing of 

Fuel Materials for the First Charge of the Dragon Reactor Experiment (Conde) 




DPR 329 

The Safety of Operations in the Dragon Fuel Element Production Building During 

the Manufacture of Thorium Fuel for the First Charge of the Dragon Reactor 

Experiment (H. Beutler et al) 




DPR 330 

An Assesment of the Carbon Transport Problem in High Temperature Gas Cooled 

Reactors (M.L. Pointud, E. Romberg) 




DPR 331 to 340 





DPR 331 

Carbon Deposition Studies (Everett, Kinsey) 




DPR 332 

Catalytic Influence of Different Metals on Corrosion Rate of Graphite (M.L. 

Pointud et al) 




DPR 333 

Experiments on the Heat Treatment of Fuel Kernals Prepared by the Sol-gel 

Process 

(L.J. Hankart) 

51





DPR 334 

Testing and Evaluation of Reactor Fuel Particles (P. Koss, H. Bildenstein) 





DPR 335 

Plutonium Fuel Cycle Studies for a Large High Temperature Graphite Moderated 

Reactor 

(H. Bruneder, P. Haubert) 




DPR 336 

Uranium - 235/Thorium Fuel Cycles in Graphite Moderated Systems (J.H. 

Blomstrand) 




DPR 337 

Dragon - Diorit Irradiation Experiment (TH Schaub, L. Dorra) 




DPR 338 

Studies on the Reprocessing and Refabrication of H.T.G.R. Fuels in the OECD 

Dragon Project (G.W. Horsley) 




DPR 339 

Thermodynamics of the Direct Gas Turbine Power Cycle for H.T.G.C Reactors 

(M.G. Von Bonsdorff) 




DPR 340 

The Cost of Coated Particle Fuel for a High Temperature Reactor Programme 

(R.A.U. Huddle et al) 




DPR 341 to 350 




52




DPR 341 

Post-irradiation Radiochemical Analysis of Changes V and VI of Pluto Loop A 

(P.E. Brown et al) 




DPR 342 

Fuel Elements for the First Core Loading of the Dragon Reactor (E. Smith) 




DPR 343 

Graphite Specimens in the Uprate Element, First Charge Position 3/1 (E.H. Voice) 




DPR 344 

Stress Concentration Around Unreinforced Circular Holes in a Plate Under 

Unidirectional Stress (A.N. Kinkead) 




DPR 345 

Fabrication of Spherical Carbide Particles (J.J. Huet) 




DPR 346 

Further Environmental Tests on Solenoid Operated Valves for the Leak Detection 

and Gas Sampling Systems (H. Woodley) 




DPR 347 

Oxidation of P.G.A. Graphite by Trace Mixtures of CO2/CO in Helium (P.J. 

Bounce, M.D. Gray, W.H. Denton) 




DPR 348 

The Development of HX30 Graphite (B. Longstaff, T.R. Jenkins, J.B Morris, L.W. 

Graham) 




53



DPR 349 

Exploratory Experiments on the Feasibilty of TH and Pu Sol-gel Particles (G. 

Vanhellemont, J. Beullens, H. Bariot) 




DPR 351 to 360 





DPR 351 

Experiments on the Irradiation of Graphite at High Temperatures (R. Blackstone 

et al) 




DPR 352 

Graphite Oxidation Under Irradiation by Traces of CO2 in a High Pressure 

Helium Carrier Gas (L. Valette, G. Van Massenhove) 




DPR 353 

Stress Concentration Adjacent to Reinforced Circular Penetrations Closely 

Pitched Transversely to an Unidirectional Stress with a Special Reference to 

Prestressed Concrete Reactor Vessels (A.N Kinkead) 




DPR 354 

A Comparative Study of Semi-Conductor Gamma Spectrometers for Scanning of 

Irradiated Dragon Fuel Elements (H. Hick) 




DPR 355 

Ninth Semi-Annual Report for the Period, 1 July - 31 December 1964 (P. Kaul) 




DPR 356 

The Manufacture of the First Charge of Fuel and Fuel Elements for the Dragon 

Reactor (R.A.U. Huddle, J.F.G. Conde, M.S.T. Price) 




DPR 357 

54



A Method of Calculating Resonance Untegrals in Graphite Moderated 

Heterogeneous Reactors (E. Fossoul, N. Meyvaert, F. Sevais) 




DPR 358 

Diffusion of Barium, Strontium and Cerium in Various Grades of Reactor 

Graphite (R.L Faircloth) 




DPR 359 

Measurements of Control Rod Worth and Excess Reactivity on the First Core of 

Dragon (I.R Cameron) 




DPR 360 

Development of Physical Methods of Fuel Analysis Semi-Annual Technical 

Report, October 1964 - February 1965 (H. Paul et al) 




DPR 361 to 367 





DPR 361 

Study of the Deposition and Properties of Pyrolytic Coatings and Fuel Particles 

(P. Lanaspeze, H. Tannenberger) 




DPR 362 

Review of the Engineering Organisation During Design and Construction of the 

Dragon Reactor (G. Franco, R.L. Terry) 




DPR 363 

Studies on the Delay and Trapping of Fission Product Noble Gases (J.C. 

Shorrock, H. Stalib) 




DPR 364 

Calculations on the Zenith Reactor with Platonium Fuelled Cones (A. Drageset) 

55






DPR 365 

Some Aspects of Carbon Transport in High Temperature Gas Cooled Reactors 

(M.R. Everett, D.V. Kinsey) 




DPR 366 

Determination of the Enriched Uranium Content of Samples by Gamma 

Ospectrometry (R.G. Pointud) 




DPR 367 

Proposals for the Periodic Inspection of the Pressure Containment System and 

Associated Plant Equipment of the Dragon Reactor (J.F.G. Conde) 




DPR 368 

Report on Work at A.E.R.E for the Dragon Project, October 1964 April 1965 




DPR 369 

The Development of an Overcoating Process for Fuel Cartridge Manufacture (G.B. 

Redding, D.N. Lamb, L.W. Graham) 




DPR 370 

Safety Document for the Dragon Fuel Element Development Laboratory Complex 

(J.R.C. Gough) 




DPR 371 to 380 





DPR 371 

Safety and Assessment for Dragon Fuel Element Production Second and 

Subsequent Charges (M. Houdaille, M.S.T. Price) 



56




DPR 372 

Basic Studies on the Catalysis of Oxidation Reactions of Graphite (Johan Lothe, 

Sigurd Melsom) 




DPR 373 

Annealing as a Post-irradiation Technique for the Study of Fission Product 

Release from Coated Particle Fuels (P. Barr, G.P. Hauser, C. Vivante) 




DPR 374 

The Use of Gas Chromatographic Methods of Gas Analysis in the Dragon Reactor 

Experiment (P.S. Gray, D.R. Owens) 




DPR 375 

Studies on Coated Particle Fuel Final Report of Work Carried Out at C.E.N Saclay 

for the Dragon Project (J. Fally) 




DPR 376 

Develpment of Physical Methods of Fuel Analysis Semi-annual Technical Report, 

March - July 1965 (H. Paul) 




DPR 377 

The Dragon Irradiation Programme in Retrospect (R.A. Saunders) 




DPR 378 

Monitoring Fludised Beds by Pressure Measurements (J. Kingdon) 




DPR 379 

The Development of the UC-10 Type Fuel Kernel for the Second Charge of the 

Dragon Reactor Experiment (R.C. Burnett, G.W. Horsley, K. Mayr) 



57



DPR 380 

Nuclear Gas Turbine Power Plant 




DPR 381 to 390 






DPR 381 

The Consolidation of Pyrolytic-carbon Coated Carbide Fuel Particles in a 

Graphite Matrix - Part II (G.H. Williams, J.B. Morris, D.W. Savage) 




DPR 382 

Graphite Irradiation in the Second Up-rated Element, First Charge Position 3/5 

(EH. Voice) 




DPR 383 

Carbon Transport in a H.T.G.C.R. Power Plant (L. Valette) 




DPR 384 

The Study of Irradiated and Unirradiated Coated Fuel Particles by the X-Ray 

Microprobe (D. Quaraert, H.W. Schleicher) 




DPR 385 

The Interpretation of Dragon Data (F.P.O. Ashworth) 




DPR 386 

Bearing Tests - A Summary of Work Done up to December 1964 (H.W. Fricker) 




DPR 387 

Fuel Irradiation Experiments in the R2 Reactor at Studsvick, Sweden (R. 

Blomquist) 


58





DPR 388 

Post Irradiation Radiochemical Analysis of Charge 8 for Pluto Loop 'A' (P.E. 

Brown, H.J. de Nordwall) 




DPR 389 

Preliminary Design of removable Integral Steam Generator Units of the Multiple 

Helically Round Tube Type for a 1250 MW (th) H.T.G.C. Reactor (P.V. Gilli) 




DPR 390 

Tenth Semi-annual Report for the Period 1st January - 30th June 1965 (F.P.O. 

Ashworth) 




DPR 391 to 400 





DPR 391 

Corrosion Rate of Graphites by CO2 and H2O - Vapour Taking into Account Inpore 

Diffusion and Temperature Gradients (E. Wicke et al) 




DPR 392 

Experiments on Preconcentration of Impurities in Helium Gas by Thermal 

Diffusion and the Measuring of Thermal Diffusion Factors (C.A. Velds, H.W. 

Grotendurst) 




DPR 393 

Dragon Operations First Quaterly Progress Report, June - August 1965 (F.J. 

Barclay) 




DPR 394 

Basic Studies on the Growth of Carbon Deposition from Carbon Monoxide on a 

Metal Catalyst (W.R. Ruston) 


59




DPR 395 

The Corrosion Behaviour of Coated Fuel Particles (N. Pollitt) 





DPR 396 

Remote Automatic Tabular Welding Devices for 18/8/1 Stainless Steel (A.R. 

Batemane, E. Barnes) 




DPR 397 

Report on the Work at A.E.R.E. for the Dragon Project, April October 1965 




DPR 398 

H.T.R. Reprocessing Study 




DPR 399 

Report on Research into the Sol-Gel Process of Preparing Carbide Fuel Particles 

(T.H. Van der Plas) 




DPR 400 

The Irradiation Performance of Triplex Coated (Pyrocarbon/sic/pyrocarbon) Fuel 

Particles (K.S.B. Rose, G.P. Hauser) 




DPR 401 to 410 





DPR 401 

Sol-gel Processes for the Preparation of the Collodial Thorium and 

Thorium/Uranium Solution (G. Cogliati) 




60



DPR 402 

Zeropower Measurements of the Temperature Coefficient of the First Dragon Core 

(J.P.H Blake, I.R. Cameron) 




DPR 403 

The Application of the Dragon Powder Mettalurgy Process to the Preparation of 

Thorium/Uranium Dioxide Fuel Kernals (L.J. Hankart, G.W. Horsley) 




DPR 404 

First Fabrication Cycle of 'Pu, C-20' Irradiation Samples (H. Bairiot et al) 




DPR 405 

Studies on Pyrolytic Carbon Coatings on Fuel Particles (H. Walther et al) 




DPR 406 

The Safety Submission for the Dragon Transfer Function Analyser (J.P.H. Blake) 




DPR 407 

Computation of Some Characteristics of Pyrocarbon Layers Deposited on Fuel 

Particles from Coating Process Measurements (P. Lanaspeze, J. Schnienwind) 




DPR 408 

Testing and Evaluation of Reactor Fuel Particles (P. Koss, H. Bildstein) 




DPR 409 

Dragon Operations Second Quaterly Progress Report (September Novemeber 

1965) 




DPR 410 

Decontaimination of Stainless Steel Loop Pipework a Peroxide Inhibited Solution 

of Oxalic Acid (J. Pattison, I.J. Davis) 


61




DPR 411 to 420 





DPR 411 

The Young's Modules of Artificial Carbons and Graphites - A discussion of 

Temperature Dependence (R.H. Knibbs) 




DPR 412 

Structural Changes in Coated Particles Irradiated Over a Wide Range of Burn-Up 

and Temperature (K.S.B. Rose, B.J. Symes, J.B. Sayes) 




DPR 413 

Fission Gas Release from High Burn-Up Carbide Fuel Kernels, (KS.B. Rose, D.J. 

Cough) 




DPR 414 

The Fabrication and Irradiation Behaviour of Plutonium - Thorium Carbide 

Coated Fuels, (B. Riley, J.N. Worth) 




DPR 415 

Constitutional Studies in the TH-PU-C System, (J.T. Dalton) 




DPR 416 

Fission Product Retention in HTR Fuel Elements, (H.J. de Nordwall, P.E. Brown, 

J. Pattison) 




DPR 417 

The Thermal Expansion Characteristics of Fuel Materials for the Dragon Reactor 

Experiment ( J.M. Milne, A. Weeden) 



62




DPR 418 

Fuel Cycles in High Temperatue Reactors on the Power Distribution in a 4-Zone 

System, (U. Nyffenegger) 




DPR 419 

The Influence of Mass Transfer on the Kinetics of Graphite Oxidation by Low 

Concentrations or Oxidising Impurities in an Inert Carrier Gas, (L. Valette, J. 

York) 




DPR 420 

The Dragon Nuclear Data Library Three (U. Nyffenegger) 




DPR 421 to 430 





DPR 421 

Experiments with Flanges Wrign Thin Feil Seals, (H. Woodley) 




DPR 422 

Recent Studies on Pyrolytic Carbon Coatings on Fuel Particles (H. Walter et al) 




DPR 423 

An Evaluation of Calibration Methods for Dragon Process Gas Chroma to Graphs 

(D.R. Owens, E. Salter) 




DPR 424 

Reprocessing of U/TH Fuel for High Temperature Gas Controlled Power 

Reactors, (G.D. Short, G. Orsenigo, E. Römberly) 




DPR 425 

High Temperature Reactors and the Dragon Project 

63





DPR 426 

Thermal Design of Gas Cooled Power Reactors - Donkey 1, (J.P. Geffroy) 




DPR 427 





DPR 428 






DPR 429 

Fission Product Determinaton on the 10MW Run for the Dragon Reactor (P.S. 

Gray, D.L. Reed, A.C. Bartlett) 




DPR 430 

The Kema Sol-Gel Process (T.H. Van der Plas et al) 




DPR 431 to 440 





DPR 431 

Studies on the Preparation of Thorium/Uranium Dicarbide and 

Thorium/Uranium Fuel Kernels by the Sol/Gel Technique in the Dragon Fuel 

Element Development Laboratory, (L.A. Podo, G.W. Worsley) 




DPR 432 

The Quality Control, Inspection and Testing of the Series I metallurgical Fuels for 

the 1st Charge of the Dragon Reactor (J.F.G. Condé, J. Holliday et al) 



64




DPR 433 

Design, Principle of Calculation and Experimental Results for the Helium 

Purification Plants Used in the Dragon Reactor Experiment (M.J. Walravens) 




DPR 434 

Fuel Cycles in High Temperature Reactors: The Approach Towards Thermal 

Breeding on the Thorium Fuel Cycle (G. Graziani) 




DPR 435 

Heat Transfer and Pressure Drop in High Temperature Helium Cooled Power 

Reactors - Parametric Survey on Internally Cooled Annular Fuel (Marien) 




DPR 436 

Corrosion Experiments on Coated Fuel Particles Using the "Xenon Release" 

Technique (N. Pollilt) 




DPR 437 

Correlation Between the Effective Diffusion Co-efficient and the Porous Structure 

in Nuclear Graphite (H.D. Beyer, P. Hugo) 




DPR 438 

Dragon Operations Third Quarterly Progress Report Dec 1965 - Feb 1966 (B.G. 

Chapman) 




DPR 439 

Record of Programme and Discussions at Symposium of Papers from Dragon 

Contractors held at A.E.R.E. Harwell, 14th - 16th March 1966 (D.J. Clough et al) 




DPR 440 

HELTOT - A programme System for Analysis of Fuel Cycles Assuming Off-Load 

Refuelling (Suitable for Uranium Systems: Burn-up, Cooling, Data-Processing), 

(H. Bruneder) 



65


DPR 441 to 450 







DPR 441 

The Safety of Operations in the Dragon Fuel Element Laboratory during 1965, 

(E.R. Batchelor et al) 




DPR 442 

The Relative Power Distribution and Integral Measurements on the First Dragon 

Core, (D.L. Reed, A.C. Bartlett) 




DPR 444 

Final Report on Research into the Sol-Gel Process of Preparing Carbide Fuel 

Particles (Contract CON/WIN/52340)(T.H. Van der Plas) 




DPR 445 

Transfer Function Investigations on First Dragon Core (J.P.H. Blake) 




DPR 446 

Facilities at Research Establishment, Risö for Post-irradiation Examination of 

Dragon Project Experiments (F. Bundgaard Larsen, Arne Sørensen) 




DPR 447 

The X-Ray Irradiation of Helium Containing Gaseous Impurities (G. Nencini, L. 

Snam) 




DPR 448 

Recent Results from the In-pile Carbon Transport Loop, (G. Van Massenhove) 




66



DPR 449 

Graphite Corrosion and Radiolysis of Carbon Dioxide in the In-pile Carbon 

Transport Loop, (A. Burkholz, D.V. Kinsey) 




DPR 450 

HTR Fuel Disposal Study (J. Wharton, A.P. Thornhill, E.S. Chapman UK Atomic 

Energy Authority) 




DPR 451 to 454 





DPR 451 

The Coating of Fuels for the "Metallurgical" Elements of the Dragon First Core 

(J.R.C. Gough, K. Mayr, E.R. Batchelor) 




DPR 452 

Design Feasibility Study for Concrete Pressure Vessel carried out by Atomic 

Power Constructions Ltd. ( Contract No. CON/WIN/56875) 




DPR 453 

Assessment Study of the Helium Purification and Handling Plant for a 532 MW(c) 

Civil High Temperature Gas Cooled Reactor (Comprimo N.V. Engineers & 

Contractors) 




DPR 454 

Engineering Assessment Study Concrete Pressure Vessel Studies Indatom Socia 

(France) 




DPR 455 to 460 





DPR 455 

67



Engineering Assessment Study Fuel Handling Equipment - Indatom Socia 

(France) 




DPR 457 

Control Rod Drive System for HTR Power Plant, (J.R. Dean) 




DPR 458 

Assessment Study of Steam Generators for a 1250 MW(th) High Temperature 

Gas-Cooled Reactor, (P.V. Gilli et al) 




DPR 459 

Main and Auxiliary Blowers for a 12500 MW(th) High Temperature Gas Cooled 

Reactor, Design Contract No. W57606 (Brown, Boveri & Co. Ltd.) 




DPR 460 

Reactor Physics Studies Leading to a Fuel Cost Survey for an HTR System with 

Low U235 Enrichment - Nuclear Power Group Ltd. (Contract No. W/57864) 




DPR 461 

Pages: 1 Report 




DPR 461 

An Experimental Investigation and Assessment of Reprocessing and 

Refabrication of High Temperature Reactor Fuel (Comitato Nazionale per 

l'Energia Nucleare) 




DPR 462 to 466 





DPR 462 

The Performance of Stainless Steel Foil Insulation in a Helium Atmosphere (P.G. 

Cowap, B.N. Furben) 

68





DPR 463 

A Classified Index of Dragon Project Reports (E. Römberg) 





DPR 464 

Assessment Study of the Power Plant Design for a 1,200 MW(th) High 

Temperature Gas Cooled Reactor (Brown, Boveri & CIE., AG) 




DPR 465 

Fabrication Costs of Prismatic HTR Fuel Elements for Feed and Breed and Low 

Enrichment Fuel Cycles (A. Klusmann, M.S.T. Price) 




DPR 466 

A Parametric Survey of the Low Enriched Uranium Cycle in a High Temperature 

Reactor (G.Mancini et al) 




DPR 467 to 470 





DPR 467 

Dragon Project Reference Design Assessment Study for a 528 MW(E) Thorium 

Cycle High Temperature Gas Cooled Reactor (G.E. Lockett, S.B. Hosegood) 




DPR 468 

Dragon Project Preliminary Assessment Study for a 528 MW(e) enriched High 

Temperature Gas Cooled Reactore (G.E. Lockett ed.) 




DPR 469 

Fuel Cycles and Reactor Physics Feed/Breed and other Throium Cycles (E. 

Schröder ed.) 



69




DPR 470 

Preliminary Summary of the Estimated Costs of Reprocessing and Refabrication 

of Fuels (G.D.C. Shorts, J. Wharton) 




DPR 471 to 480 





DPR 471 

Heterogeneous Fuel Cycle Calculations on Some Selected HTR Low Enriched 

Uranium Systems, (H. Gutman, H. Schoeber) 




DPR 473 

Dimensional Changes in Graphite During High Temperature Irradiation in the 

High Flux Reactor REN, Petten, (R. Blackstone, L.W. Graham) 




DPR 474 

The First Year at Full Power (B.G. Chapman, F.D. Danby) 




DPR 475 

Introduction to the High Temperature Gas-Cooled Reactor Concept - The THTR 

Prototype (R. Schulten, H.G. Schafstall, F. Schmieder, K. Hintermann, V. 

Hennings, H.J. Stöcker et al) 




DPR 476 

Utilisation of Fuel Resources in Different Reactor Types, (P. Marien) 




DPR 477 

Fuel Cycles in High Temperature Reactors the Influence of Fuel Elements. 

Heterogenity on a Partly Enriched Uranium Cycle (J.H. Blomstand, H. Bruneder) 



70




DPR 478 

Fuel Cycles in High Temperature Reactors Complete core Replacement and Part 

Loaded Systems in the U-235/Th and U235/U/238 Cycles, ( H. Bruneder) 




DPR 479 

The Practical Application of Theoretical Studies to the Tilting-Pad Gas Bearing, 

(J. Corniglion) 




DPR 480 

The Dragon First Charge THTR Element (B. Gardham, A.J. Eycott) 




DPR 481 to 490 





DPR 481 

Dragon Loops in R2, Charge 9, (Ex P-R2-5412), (Per Svensson) 




DPR 482 

Compatibility of Constructional Materials (A.B. Knutsen et al) 




DPR 483 

Dragon Operations Group - 4th Quarterly Progress Report March - May 1966 

(D.G. Chapman) 




DPR 484 

Laboratory Experiments Carried out on Clam Seals, (H.J. Woodley) 




DPR 485 

Coated Particle Fuel Production Cost Code COPACO - A Computer Programme for 

the Study of the Fabrication Influences to Coated Particle Production Costs (A. 

Klusmann, M.S.T. Price) 

71





DPR 486 

Seizure Tests on a Dragon Articulated Control Rod (H.J. Woodley) 





DPR 487 

The Measurement of Sub-VPM Levels of Water and Hydrogen Under Plant 

Conditions using a Pressurised Goldsmith Electrolytic Hygrometer, (P.S. Gras) 




DPR 488 

Dragon Operations Group 5th Quarterly Progress Report, June to August 1966 

(B.G. Chapman) 




DPR 489 

Aspects of the Replacement Elements in the 2nd Charge of the Dragon Reactor, 

(M.S.T. Price, E. Smith) 




DPR 490 

11th Semi-Annual Report for the Period 1st July 1965- 31 December 1965, 

(F.P.O. Ashworth) 




DPR 491 to 500 





DPR 491 

Carbon Transport Studies for Helium Cooled High-Temperature Reactors, (M.R. 

Everett) 




DPR 492 

An Assessment of a Low Throughput Coated Particle Production Line 

Fabrication, U-235/T11 Fuel, (A. Klusmann, M.S.J. Price) 



72




DPR 493 

Report on work at A.E.R.E. for the Dragon Project, Nov 1965 - Oct 1966, (Atomic 

Energy Research Establisment) 




DPR 494 

The Determination of Total Carbon in Silicon Carbide Coated Dragon Fuel 

Particles,(R.E. Siddall, D.L.G. Smith) 




DPR 495 

Convective Heat Transfer Correlations for Use with Helium at High Heat Fluxes, 

(P.J. Marien, A.D. Richards) 




DPR 496 

Experiments with Stand-Pipe Closure and Stand-Pipe Charge Machine 

Connections for Proposed HTGC Power Reactor (H.J. Woodley) 




DPR 497 

Post-Irradiation Gas Release Measurements on Fuel Elements from the first 

20MW run on the Dragon Factor, (L. Aumüller, P. Barr et al) 




DPR 498 

A Pulsed Ultrasonic Thermometer, (E.G.H. Mobsby) 




DPR 499 

Bacon Anisotropy Factor and Crystalline Sizes Measurements on Pyrocarbon 

Specimens (G. Tassone) 




DPR 500 

The Kenetics of Carbon Deposition Reactions in High Temperature Gas Cooled 

Reactors, (M.R. Everett) 



73


DPR 501 to 510 






DPR 501 

Dragon Plant Record - The Primary Circuit, (J. Pugh, W.E. Simmons) 




DPR 502 

Dragon Plant Record - Helium Coolant Distribution, (J. Pugh) 





DPR 503 

Dragon Plant Record - Graphite Assemblies Other Than Fuel Elements, (E. Smith) 




DPR 504 

Dragon Plant Record - Control Mechanisms (J.R. Dean) 




DPR 505 

Dragon Plant Record - The 25 Ton Circular Track Crane, (H.H. Westbrook) 




DPR 506 

General Plant and Facilities Services Building, (P. Acciarri, C.J. Edney) 




DPR 507 

The Dragon Core, (E. Smith) 




DPR 508 

Gas Disposal System, (W.E. Simmons, D.F. Hill) 




74


DPR 509 

Leak Detection and Gas Sampling Systems, (H.F. Enzmann) 




DPR 510 

Dragon Plant Record, (P.L. terry, N.T. Barrett) 




DPR 511 to 516 





DPR 511 

Clean Helium System, (E.J. Mitchell et al) 




DPR 512 

Fuel Element Purge and Monitoring System, (E.J. Mitchell et al) 




DPR 513 

The Fission Product Trapping System, (F. Taylor, R. Read et al) 




DPR 514 

Helium Purification System 




DPR 515 

Reactor Plant Instrumentation and Control, (P. Acciarri, M. de Bacci et al) 




DPR 516 

The Breathing Air Installation, (Derek Davis) 




DPR 521 to 530 



75






DPR 521 

Metal Fission Product Analysis for the Dragon High Temperature Gas Cooled 

Reactor - Charge 1 and Irradiation Loops (G.F.F.J Preinreich) 




DPR 522 

Basic Studies on the Growth of Carbon Deposition from Carbon Monoxide on a 

Metal Catalyst (M. Warze) 




DPR 523 

Fission Products in Dragon Fuel Rod 000-7, (P.E. Brown et al) 




DPR 524 

Silicon Carbide Deposited from Methyldichlorosilane in a Fluidised Bed, (R.L. 

Beatty, D. N. Lamb) 




DPR 525 

The Manufacture of Plutonium Fuelled Fission Product Retaining Coated Particles 

for Irradiation in the Dragon Reactor Experiment, (O.W. Horsley, R.A.U. Huddle) 




DPR 526 

High Temperature Irradiation Experiments on Plutonium Bearing Coated Particle 

Fuel, (P. Barr et al) 




DPR 527 

The High Temperature Corrosion of Nimonic - 75 and Various Steels in Gases at 

Low Partial Pressures, (A.B. Knutsen, J.F.G. Condè, K. Piere) 




DPR 528 

The Preparation of the First Series of "Metallurgical Elements for the Dragon 

Reactor Consolidation and Assembly", (A.J. Eycott) 


76





DPR 529 

Prestressed Concrete Vessels Suitable for Helium High Temperature Reactors, 

(G.E. Lockett, A.N. Kinkead) 




DPR 530 

Study of Catalytic Decomposition of Carbon Monoxide on Pure Iron, Mild Steels 

and Alloyed Steels, (M. Warzee, C. Sonnen, J. Hennaut, W.R. Ruston) 




DPR 531 to 540 





DPR 531 

Dragon Operations Group 6th Quarterly Progress Report Sept - Nov 1966 




DPR 532 

Corrosion of Mild Steel Circuits in 1.5% lithium Sulphate Solution, under Heat 

Transfer Conditions, (P.S. Gray, G. Gilling, A.B. Thorneycroft) 




DPR 533 

Review of Dragon Safety 1966, (B.G. Chapman) 




DPR 534 

Plutonium Coated Partide Production for HTR Fuel Elements, (H. Bairist, A. 

Klusmann, M.S.T. Price) 




DPR 535 

The Recovery of 0235 from Reject and Surplus Dragon Fuels, (F.M. Bolton, T.A. 

Davies, G.W. Horsley) 



77




DPR 536 

Method for Measuring the Uranium Contamination in Fuel Particle Coatings, (B. 

Chinaglia) 




DPR 537 

Materials for the Boiler Tubes of AHTGC Power Reactor, (J.F.G. Condé) 




DPR 538 

Measurement of the Burn-up of the Dragon First Charge Fuel Elements Using 

Gamma Spectrometry, (A.C. Bartlett, D.L. Reed) 




DPR 539 

On the Qualification of Fission Product Release, (G. Preinreich) 




DPR 540 

HTR Fuel Reprocessing and Refabrication Study, (J. Wharton) 




DPR 541 to 550 





DPR 541 

Dragon Reactor, Log D.C. Channels - Investigations into their Unreliability up to 

Nov. 1966, (M.J. Walravens) 




DPR 542 

The Preparation of Porous UO2 Fuel Kernels from U3O8 Powder for a HTR 

Utilising the Low Enrichment Cycle, (G.W. Horsley, R.C. Burnett) 




DPR 543 

Development of Plutonium Fuelled Coated Particles for Irradiation in the Dragon 

Reactor Experiment (Belgo Nucléaire) 

78






DPR 544 

Results of the Injection of Impurities into the Dragon Reactor Primary Coolant, (M. 

Carlyle, D.V. Kinsey) 




DPR 545 

The Thermal Conductivity of Annual Beds of Coated Fuel Particles, (J.H. Day) 




DPR 546 

Thermal Performance of the Dragon Reactor, (W.S.A. Black, C.L. Brown, I.S. 

Green) 




DPR 547 

The Examination of a Dragon Reactor Primary Heat Exchanger After Corrosion 

Failure, (P.S. Gray, J.D. Hamilton, D.L.G. Smith) 




DPR 548 

The Containment Safety of the Dragon Reactor, (G.R. Cullington) 




DPR 549 

Safety Submission for Operation of the Dragon Reactor at 20 MW, (G.R. 

Cullington) 




DPR 550 

Some Elastic and Thermal Properties of Fuel, Particles in Bulk, (Eric Voice) 




DPR 551 to 560 




79




DPR 551 

Production of Porous UO2 Kernels by Heat Treatment of Powder Metallurgy 

U3O8 Microspheres, (T.M. Washburn, R.C. Bunett) 




DPR 552 

Helium Utilisation on Dragon During the Approach to Powder and First Charge 

Irradiation, (H.B.F. Gow, P.S. Gray, J.D. Hamilton) 




DPR 553 

Impurity Removal from the Dragon Reactor during Initial Commissioning (P.S. 

Gray, K.M. Noset, D.R. Stonier) 




DPR 554 

The Removal and Replacement of a Primary Heat Exchanger Tube Bundle and 

Circulateor on the Dragon Reactor, (P.P. Capp C. Watts, P.S. Gray) 




DPR 555 

Pressure Drop Measurements on Dragon Fuel Element Spikes (R.C. Hollick, H.J. 

Woodley) 




DPR 556 

Dimensional Changes of Graphite Specimans - Irradiated in Dragon Fuel 

Element 700, (M.R. Everett, D. Lamb) 




DPR 557 

Irradiation Experiments on Low Enrichment Fuel: LEHPD 1 and STUDSVIK 

Loops, Charge 15, (P. Barr, H. Hagen) 




DPR 558 

Preliminary Study for a 630 MW(E) Low Enriched Homogeneous High 

Temperature Gas Cooled Reactor (G.E. Lockett, S.B. Hosegood) 



80




DPR 559 

The Comparison of Carbon-Atom Displacement Rate in Graphite in the Dragon 

Reactor, The Petten HTR, and Low Enrichment, HTR (D.L. Reed) 




DPR 560 

The Thermal Cycling of Bonded Fuel Particles (Eric Voice) 




DPR 561 to 569 





DPR 561 

Operational Data for Charge 1, (C. Hunt, M.D. Joyce) 




DPR 562 

The Measurement of High Temperature Irradiation Creep in Graphite, R. 

Blackstone 




DPR 563 

Further Optimisation Studies of Experimental Dynamic Responses Measured on 

the HTGG Dragon Reactor, (J.D. Cummins) 




DPR 564 

Measurement of Fission Product Deposition on the Heat Exchangers and Gas 

Circulators of the Dragon Reactor, (P.E. Brown, R.H. Flowers et al) 




DPR 565 

FIPDIG - A One Dimensional Time Dependent Fission Product Diffusion Code, (G. 

Preinreich) 




DPR 566 

81



Some Graphite Corrosion Problems Related to Helium Cooled High Temperatue 

Reactors (G.H. Helsby, M.R. Everett) 




DPR 567 

The Comparison of Carbon-Atom Displacement Rate in Graphite in the Dragon 

Reactor, the Pettern HTR and Other Reactors, (D.L. Reed) 




DPR 568 

Safety Aspects of the Fuel Elements to Make-up the 3rd Charge of the Dragon 

Reactor, (M.S.T. Price, E. Smith) 




DPR 569 

The Pyrolysis of Methane in a Bed of Particles, (Eric Voice) 




DPR 571 to 580 





DPR 571 

An Interim Report on Fission Product Distribution in Dragon after the First 20 

MW run, (H.J. de Nordwall, P.E. Brown) 




DPR 572 

The Safety of Operations in the Dragon Fuel Element Fabrication Laboratory 

During 1966, (E.R. Batchelor, C.R. Broots) 




DPR 573 

Fuel Cycles in High Temperature Reactors: The Thorium Cycle in One-load 

Refuelled Systems (J.H. Blomstrand) 




DPR 574 

Some Observations of Fuel Particle Coatings at very High Magnification, (Eric 

Voice) 

82






DPR 575 

A Fuel Cycle Theory with 2 Computer Programmes for On-load Refuelled Thermal 

Converter Reactors, (J.H. Blomstrand et al) 




DPR 576 

The Non-Destructive Testing of Graphite Fuel Element Components for the 

Dragon Reactor Experiment, (J.F.G. Condé, J. Holliday) 




DPR 577 

A Summary of the Results Obtained in the Quality Control Inspection and 

Testing of Fuel Materials for the 2nd Charge of the Dragon Reactor, UC-10 Driver 

Fuel, (J.F.G. Condé, J. Holliday) 




DPR 578 

Analytical Treatment of a Transient Method for Determination of the Thermal 

Conductivity of a Hollow Right Cylinder of Solid Material, (M. Von Bonsdorff) 




DPR 579 

Evaluation of the Data from the First Dragon Charge, (F.P.O. Ashworth, G.F.F.J. 

Freinreich) 




DPR 580 

The Quality Control- Inspection and Testing of Fuel Materials for the Two 

Uprated Fuel Elements (J.F.G. Condé, J. Holliday et al) 




DPR 581 to 590 





DPR 581 

Self-Sustaining Mixed Fast and Thermal Reactor Systems, (C.A. Rennie) 


83





DPR 582 

Dragon Operations Group, 7th Quarterly Progress Report, Dec 1966-Feb 1967, 





DPR 583 

The Post-Irradiation Metallographic Examination of Fuel Cartridges from 2 

Uprated Fuel Elements Discharged from the Dragon Reactor, (L.J. Hankart) 




DPR 584 

Metallic specimens to be Exposed to the Coolant in the Dragon Reactor for 

Monitoring and Experimental Purposes, (J.F.G. Condé, J.G. Dickson) 




DPR 585 

Heat Transfer Aspects of Coated Particle Fuel and Test Elements, (K. Bongartz) 




DPR 586 

The Metallurgical Examination of a Primary Heat Exchanger Tube Bundle from 

Loop "C" of the Dragon Reactor, (J.F.G. Condé, J. Holliday, H. Oates) 




DPR 587 

Overcoating and Pressing Processes, (A.J. Eycott) 




DPR 589 

The Post-irradiation Metallographic Examination of (TH,U) C2 and "UC-10" Fuels 

from Fuel Elements 134 and 143 Irradiated in the 1st Charge of the Dragon 

Reactor, (L.J. Hankart) 




DPR 590 

A Resonant Probe Ultrasonic Thermometer, (E.G.H. Mobsby) 



84


DPR 591 to 600 







DPR 591 

Pressure Drop Measurements made on a Dragon Heat Exchanger Fitted with 

Various Designs of Water Catch-Pot, (H.J. Woodley) 




DPR 592 

Dragon Operation Group 8th Quarterly Progress Report, March 1967- May 1967, 





DPR 593 

Dragon Operations Group 9th Quarterly Progress Report June - Aug 1967, (B.G. 

Chapman) 




DPR 594 

Dragon Operations Group10th Quarterly Progress Report Sept - Nov 1967, (B.G. 

Chapman) 




DPR 595 

Calculation of the Release of Fission Products from Coated Particles, (H. Walther) 




DPR 596 

Calculation of the Release of Fission Products from Triplex Coated Particles, (H. 

Walther) 




DPR 597 

Calculation of the Release of Fission Products from Coated Particle Fuels, (H. 

Walther) 




DPR 598 

85



Parameter Estimation from Dragon High Temperature Gas Cooled Reactor 

Dynamic Experiments, (J.D. Cummins) 




DPR 599 

The Development of Advanced Coated Particle Fuels, (J.R.C. Gough, K. Mayr) 




DPR 600 

Brown Boveri High Temperature Reactor Project - Annual Progress Review, 1967- 

68 




DPR 601 to 610 





DPR 601 

Preliminary Investigation of the Fuel Temperatures in a 630 MW(e) Low Enriched 

Homegeneous High Temperature Gas Cooled Reactor, (U. Weicht) 




DPR 602 

Safety of Operations in the Dragon Fuel Element Fabrication Laboratory during 

1967, (E.R. Batchelor et al) 




DPR 603 

Graphite Irradiation Experiments in HFR Petten, (R. Blackstone, E. Voice) 




DPR 604 

Stress Analysis in Coated Fuel Particles, (H. Walther) 




DPR 605 

Advanced and High Temperature Gas Cooled Reactors - Symposium Papers 



86




DPR 606 

Considerations Relating to Experiments on the Evaporation of Fission Products 

from Graphite, (P.R. Rowland) 




DPR 607 

A Flexible System for Automatic Gas Flow and Temperature Control of Coating 

Furnaces, (R. Lefevre) 




DPR 608 

Metallographic Examination of Element 700 met. 1A the First Metallurgical 

Element of the First Charge, (L.J. Hankart) 




DPR 609 

The Dragon 2nd Charge THTR Elements, (T. Görgenyi et al) 




DPR 610 

ORNL Sol Gel Coated Particle Fuel Irradiation in Dragon Second Charge, (R.L. 

Beally, A.J. Eycott et al) 




DPR 611 to 620 





DPR 611 

A Summary of Results on the Quality Control Testing and Inspection of U02/10C 

Driver Fuel for the 3rd Charge of the Dragon Reactor Experiment, (J. Holliday et 

al) 




DPR 612 

Practical Details of the Ultrasonic Thermometers being Installed in the Dragon 

Reactor, (E.G. Mobsby) 




87



DPR 613 

Studies on the Behaviour of Miscellaneous Alloys in the Gaseous Atomosphere of 

a High Temperature Reactor 




DPR 614 

Operational Data for Charge 11, (C. Hunt, L.J. Poston) 




DPR 615 

Resonance Absorption in Materials with Grain Structure - Equivalence Relations 

(J. Journet) 




DPR 616 

Silicon Carbide as a Fission Product Barrier in Nuclear Fuels, (C.H. Voice) 




DPR 617 

Temperature Coefficients and Stability Investigation of AHTR Survey, (J. Journet, 

F. Woloch) 




DPR 618 

A Study of Distribution Effects of Water Falling from a Failed Heat Exchanger 

onto the Dragon Reactor Core, (H. Woodley) 




DPR 619 

Some Development Studies for the Coved Wall Prestressed Concrete Pressure 

Vessel, (A.N. Kinkead) 




DPR 620 

Reduction Sintering of U3O8 Microspheres in a Fluidised Bed Furnace to Produce 

Porous UO2 Kernels, (T.N. Washburn) 




DPR 621 to 630 


88






DPR 621 

Dragon Operations Group 20th Quarterly Progress Report March to May 1968, 

(F. Danby) 




DPR 622 

Helium Coolant Chemistry and the Basic Design of a Low Molecular-Sieve H2O 

and CO2 Adsorption Plant for Low Inlet Partial Pressures Using Dragon Project 

and Other Published Experimental Data for the Coarse Purification of the Helium 

Coolant Used in a 1,500 MW(th) High Temperature Gas-Cooled Power Reactor, 

(C. Harper, D.V. Kinsey) 




DPR 623 

The High Temperature Experiment in Dragon Charge 2, (K. Röllig) 




DPR 624 

A Non-Destructive Testing Technique for Evaluating the Density Distribution of 

Heavy Metal in Nuclear Fuel Elements, (J. Holliday, J.C. Hedderly) 




DPR 625 

Stability Behaviour of Steam Generators with Upward Flow of Helium (Final 

Report Contact No. 58817), (K. Fritz, P.V. Gilli) 




DPR 626 

Burn-up Estimation During Reactor Operation, (C. Hunt, S. Howell) 




DPR 627 

Dragon Reactor Fuel Handling Equipment, (A.N. Kinkead, P.C. Smith) 




DPR 628 

Description of the Computer Codes FIPDIG, (G. Preinreich) 


89





DPR 629 

The Migration of Uranium Through Complex Coated UO2 Particles Interim Report, 

(K. Röllig) 




DPR 630 

Dragon Operations Group 11th Quarterly Progress Report, Dec 1967 Feb 1968, 

(F.D. Danby) 




DPR 631 to 640 





DPR 631 

Dragon Operations Group 13th Quarterly Progress Report, 1st June 31st Aug 

1968, (W.B. Safter) 




DPR 632 

Noise Spectra Measured on the Dragon Reactor Primary Heat Exchanges, (J.D. 

Cummins) 




DPR 633 

Contamination in the Coating of Fuel Particles, (R. Lefevre) 




DPR 634 

A Simple and Rapid Method for Estimating the Mean External Diameter and 

Density of Spherical Particles, (R. Lefevre) 




DPR 635 

Improved Primary Circuit Maintenance Techniques: The Removal of E. Primary 

Heat Exchanger, (P.S. Gray) 



90




DPR 636 

The Fabrication of Fuel Pins for the 40% Enriched Power Reactor Test Element, 

(no. 406), (J.R.C. Gough) 




DPR 637 

The Development of a Meniscous Bonding Process for Coated Particle Fuel, 

(J.R.C. Gough) 




DPR 638 

Dragon Operations Group 14th Quarterly Progress Report, Sept. - Nov. 1968, 

(B.G. Chapman, W.B. Salter) 




DPR 639 

New Methods for the Investigation of Radioisotope Transport in a Gas-Cooled 

Reactor, (P.R. Rowland) 




DPR 640 

A Gain Stabilised Semi-Conductor Compton Spectrometer, (A.C. Bartlett, D.L. 

Reed) 




DPR 641 to 649 





DPR 641 

Operational and Post-Irradiation Fuel Utilisation Determinations in the Dragon 

Reactor, (A.C. Bartlett, C. Hunt, D.L. Reed) 




DPR 642 

The Correlation of Graphite Irradiations in the High Flux Reactor Petten and in 

High Temperature Reactors, (M.R. Everett, R. Blackstone) 




91



DPR 643 

Measurement of the Physical and Mechanical Properties of Pressed Gilsocarbon 

Graphite, (Dragon ref. 95), (M. Gateau) 




DPR 644 

Thermal Gradient Experiments on Stress Failure of Tubes of Gilsocarbon 

Graphite, M. Gateau) 




DPR 645 

Experiments with "c" type Avica seals, (A. Stringer) 




DPR 646 

Irradiation Data on Gilsocarbon Graphites for High Temperature Nuclear 

Reactors, (R. Blackstone, M.R. Everett) 




DPR 647 

Fission Products in the Dragon Directly Cooled Element No. 710, (P.E. Brown, 

F.J. Sandalls, A.J. Inns, J. Gouk, H. Baker) 




DPR 648 

Theoretical Investigations of Coated Particle Fuel Performance by Stress 

Analysis, (K. Bongartz) 




DPR 649 

Calculation of Fission Product Release from a Power Reactor, (G. Mielken) 




DPR 651 to 660 





DPR 651 

A Theoretical Analysis of Flow Instabilities in the Dragon Primary Heat 

Exchanges, (A.L. Davies) 

92






DPR 652 

The Influence of Fabrication Parameters on the Incidence of Spearhead Attack on 

Coated Particle Fuel, (R.A.U. Huddle, K.W. Jones, K. Mayr) 




DPR 653 

Fretting Experiments Carried out on Dragon Heat Exchanger Components, (D. 

Barnes, H. Woodley) 




DPR 654 

X-Rays Absorption Corrections for Bacon Ansiotropy Factor Measurements on 

PYC, (G. Tassone) 




DPR 655 

A Summary of the Work on the U3O8 Route for Porous UO2 Kernel Preparations, 

(H. Chantot) 




DPR 656 

Economics and Fuel Cycles of Homogenous Design HTR's with Loose-Bonded 

Low Enrichment Fuel, (H. Gutmann, J.J. Devos et al) 




DPR 657 

Dimensional and Physical Property Changes of High Temperature Reactor 

Graphites Irradiated at Temperatures in the Range 600-1200 degrees celsius, 

(M.R. Everett, R. Blackstone, L.W. Graham, R. Manzel) 




DPR 658 

Methods for the Chemical Analysis of Dragon Fuels, (R.E. Siddall, D.L.G. Smith, 

G.T. Taubman et al) 




DPR 659 

93



Dimensional and Physical Property Changes of Graphite Specimens Irradiated in 

Dragon Fuel Element 701, (R. Manzel) 




DPR 660 

The Dracule, an Equipment for the Study of the Radiosotope Content of Hot-Gas 

Reactor Coolant, (P.R. Rowland, B. Pitchword et al) 




DPR 661 to 667 





DPR 661 

Operating Experience with the Dragon Steam Generators, (J. Holzner) 




DPR 662 

Stresses in the Graphite Fuel Tubes of a High Temperature Gas Cooled Reactor, 

(A. Jezernik, J.L. Head) 




DPR 663 

Developments in the Electrolytic Etching of Pyrolytic Silicon Carbide, (M. Wills) 




DPR 664 

An Assessment of the Operating Characteristics of the Proposed Modified 

Secondary Coolant Circuit for the Dragon Reactor, (A.A. Cooper) 




DPR 665 

High Temperature Radiation Induced Creep in Graphite, (R. Blackstone, L.W. 

Graham, M.R. Everett) 




DPR 666 

Performance of Thermal Insulation Immersed in Helium, (A.N. Kinkead, B.E. 

Pitchford) 


94





DPR 667 

The Economics of the 1st Generation High Temperature Reactors and Future 

Prospects, (H. Gutmann, G. Graziani et al) 




DPR 670 to 680 





DPR 670 

High Temperature Power Reactor Design, (S.B. Hosegood) 




DPR 671 

Physics Aspects of HTR Core Design, (H. Gutmann) 




DPR 672 

HTR Fuel Element Design (E. Smith) 




DPR 673 

The Dragon Project Programme of Core Materials Development for High 

Temperature Power Reactors, (R.A.U. Huddle) 




DPR 674 

The Fabrication of Poros and UO2 Microspheres, (R. Baschwitz) 




DPR 677 

The Deposition and Structure of Pyrolytic Silicon Carbide, (E.H. Voice, D.N. Lamb) 




DPR 678 

The Present State of Fuel Consoldiation in Dragon, (E.H. Voice, J.R.C. Gough) 

95





DPR 679 

The Pre-Irradiation Testing of HTR Fuels, (J. Holliday, T. Görgenyi et al) 




DPR 680 

Experience with the Production of AVR-Fuel Elements, (K.G. Hackstein) 




DPR 682 to 690 






DPR 682 

A Study of Fission Product Release From Compacted Uranium/Thorium Coated 

Particle Fuel, (F. Barr, P.E. Brown) 




DPR 683 

A Model for Stress Analysis in Coated Fuel Particles, (H. Walther) 




DPR 685 

Graphite Behaviour in Relation to Fuel Element Design, M.R. Everett, R. 

Blackstone et al) 




DPR 686 

The Irradiation Behaviour of Coated Particle Fuel Compacts, (M.R. Everett et al) 




DPR 689 

Factors Affecting the Cost of Fabricating HTR Fuel, (D.F.I. Bishop et al) 




DPR 690 

96



The Influence of Fuel and Fuel Element on Power Reactor Generating Costs, (H. 

Gutmann) 




DPR 692 to 700 





DPR 692 

The Fabrication of Porus UO2 Microspheres for Low Enrichment HTR Fuel 

Cycles, (R.C. Burnett, H. Chantot, T.A. Davies) 




DPR 693 

Irradiation Experience with UO2 Coated Particle Fuel, (P. Barr, P.E. Brown) 




DPR 694 

Stress Analysis of the KSH-Particle and of Dragon Particles Irradiated in the 

Dounreay Fast Reactor, (K. Bongartz) 




DPR 696 

Dragon High Temperature Gas Cooled Reactor Dynamic Response 

Measurements, April 1969 and Optimum Parameter Fitting, (J.D. Cummins) 




DPR 697 

The Loading of the Miscellaneous Metallurgical Elements, (E. Formann, R. 

Rotterdam) 




DPR 698 

Long-Time Annealing Tests with Variants of Dragon Ref. Type 1 Fuel, (R. 

Rotterdam) 




DPR 699 

Graphite Materials Data for High-Temperature Nuclear Reactors, (M.R. Everett, 

R. Blackstone) 

97





DPR 700 

A Model of Depressurisation of a Steam Cycle HTR, (G. Soubelet) 




DPR 701 to 710 






DPR 701 

Removal of Chloride Impurity from Dragon Reactor Secondary Circuit Coolant, (D. 

Brown-Smith, N. Forsyth) 




DPR 702 

The Distribution of Fission Products in a High Temperature Gas-Cooled Reactor, 

(P.R. Rowland, M. Carlyle, G.C. Soubelet) 




DPR 703 

Temperature Co-Efficients of the 1st Dragon Charge, (H. Gutmann, F. Woloch) 




DPR 704 

The Equivalence Theorem for Resonance Integral Calculations of Granular Fuel 

in Annular and Teledial Geometrics, (F. Woloch) 




DPR 705 

A Comparison of the Stresses in HTR Fuel Tubes made of Dragon-Peciney GA 

and Pressed Isotropic Gilsocarbon Graphites, (J.L. Head, A. Jezernik) 




DPR 706 

The Characterisation of Uranium Oxide Powders for the Fabrication of Poros UO2 

Microspheres by Powder Agglomeration, (R. Baschwitz) 



98




DPR 707 

Dragon Operations Group 15th Quarterly Progress Report, Dec 1968-Feb 1969, 

(W.B. Salter) 




DPR 708 

The Post-Irradiation Examination of the D7 (XPR-2) Fuel Element, (L.J. Hankart, 

K. Mayr, J.Evans) 




DPR 709 

Dragon Operations Group 17th Quarterly Progress Report, June - Aug. 1969, 

(P.D. Capp) 




DPR 710 

Dragon Operations Group 16th Quarterly Progress Report, March - May 1969, 

(W.B. Salter) 




DPR 711 to 720 





DPR 711 

Dragon Project Engineering Studies on the Direc Cycle HTR, (S.B. Hosegood, G.E. 

Lockett, R.F. McIver) 




DPR 712 

Control and Safety Studies for an HTR Gas Turbine System, (J.R. Dean, G. 

Preinreich, G.C. Soubelet) 




DPR 715 

Fission Product Release Measurements in the Dragon Reactor Charge 11, (R.M. 

Carlyle, D.R. Stonier) 




99



DPR 718 

Dragon Operations Group 18th Quarterly Progress Report, Sept. to Nov. 1969, 

(W.B Salter) 




DPR 719 

Dragon Operating Experience, (B.G. Chapman) 




DPR 720 

Codes Muther 3 & Muther 4: 3 Dimensional Codes for the Calculation of Power 

Density in Reactors with Partly Inserted control Rods, (J.L. Picoli) 




DPR 721 to 730 





DPR 721 

Brown Boveri-Dragon Project Collaboration Agreement 




DPR 722 

Gamma Spectrometric Examination of Irradiated Dragon Fuel Elements, (H. Hick, 

H. Nabielek, J. York) 




DPR 723 

Temporary Effects Due to the Eccentricity of Fuel Compacts in various, HTR Fuel 

Elements, (G. Mancini) 




DPR 724 

Post-Irradiation Examination of Coated Fuel Particles: Determination of C5137 

release, (H. Bildstein) 




DPR 725 

Determination of the Distribution of Metallic Fission Products in Fuel Particle 

Coatings by the Ion Sputtering Technique, (G. Betz et al) 

100






DPR 726 

Dragon Project Metals Corrosion Programme Description of the Helium Rig at 

CHR, Oslo, (J.G. Dickson, M.R. Everett, K. Boye) 




DPR 727 

Dragon Operations Group 19th Quarterly Progress Report, Dec 1969 Feb 1970, 

(W.B. Salter) 




DPR 728 

Determination of Gases in Low Enriched Coated Oxide Particles, (H. Bildstein, A. 

Strigl) 




DPR 729 

MUPO-B and its Auxiliary Programmes, (H.R. Schober) 




DPR 730 

Experimental Results from the UKAEA Reactor Physics Programme on Low 

Enrichment HTR Lattices at AEE, Winfrith, (I. Johnstone, V.E. della Loggia) 




DPR 731 to 740 





DPR 731 

Methods for the Pre-Irradiation Examination of Low Enriched UO2 HTR Fuels, (J. 

Holliday, D.L.G. Smith) 




DPR 732 

Fission Product Release Measurements in the Dragon Reactor Cores 1-7 of 

Charge 111 by (R.M. Carlyle, D.R. Stonier) 



101




DPR 733 

Evaluation of Gamma-Spectrometric Fission Product Release Measurements on 

2nd Charge Centre Rods, (H. Nick, H. Nabielek, J. York) 




DPR 734 

Tables of Thermophysical Properties of Helium, (H. Petersen) 




DPR 735 

Consolidation of Fuel Campacts with High Loading of Coated Particles, (M.F. 

Hroual) 




DPR 736 

The Behaviour of Iodine Isotopes in a High Temperature Gas Reactor Coolant 

Circuit, P.R. Rowland, W.E. Browning, M. Carlyle) 




DPR 737 

Using the High Temperature Reactor for Power Generation Below 500 MW(e), 

(G.E. Lockett) 




DPR 738 

Investigation of the Influence of Fabrication Parameters in Matrix Fuel Compact 

Fabrication, (Y. Barbier) 




DPR 739 

XEBASS-2 - "Equilibrium Fuel Cycle Programme for Continously On-Load 

Refuelled High Temperature Reactors", (J. Pedersen, H.R. Schober) 




DPR 740 

The Effect of the Kernel Material and of the Coating Structure on the Migration of 

Uranium in Fuel Particles, (B. Chinagalia) 



102


DPR 741 to 750 







DPR 741 

Core Corrosion Following a Large Water in Leakage into the Dragon Primary 

Circuit, (N. Forsyth, P. S. Gray) 




DPR 742 

Influence of the CO Partial Pressure on the Performance of Low Enriched UO2 

Coated Partide Fuel, (R. Rotherdam) 




DPR 743 

Further Measurements of Fission Product Deposition on the Heat Exchanges and 

Gas Circulators of the Dragon Project, (H.T. Banker, P.R. Rowlands et al) 




DPR 744 

The Presence of AG-111 in the Dragon Primary Coolant Circuit, (P.R. Rowland et 

al) 




DPR 745 

Diffusion of an Adsorbable Isotope Vapour Through Porous Graphite in the 

Helium, (P.R. Rowland) 




DPR 746 

Resovoir Models for Fission Product Retention, (P.R. Rowland) 




DPR 747 

2 DIFIP - A, 2 Dimensional Code for the Calculation of Distribution and Release 

of Fission Products in HTR Cores, (G.G. Nastri, P.R. Rowland) 




DPR 748 

103



TAPIR - COCO - DELTAP. 3 Computer Programmes for the Thermal Analysis of a 

Reactor Core Containing Internally and/or Externally Gas Cooled Prismatic Fuel 

Elements, (U. Weicht, W. Müller) 




DPR 749 

Interim Report on Fuel Pin Bowling - Initial Method, (A.N. Kinkead) 




DPR 750 

Metal Fission Product Release from a Notional 1,500 MW(th) HTR Core, (R.E.S. 

Gray, G. Mancini) 




DPR 751 to 760 





DPR 751 

The High Temperature Gas Cooled Reactor - A Process Heat/Electrical Energy 

Source for a Large Steelworks, (S.B. Hosegood, D.A. Hawkes et al) 




DPR 752 

A High Temperature Graphite Irradiation Creep Experiment in the Dragon 

Reactor, (R. Manxel, M.R. Everett, L.W. Graham) 




DPR 753 

Some HTR Fuel Pin Stress Problems, (A.N. Kinkead) 




DPR 754 

The Establishment of Complete Fission Product Inventories for Irradiated Fuel 

Elements, (H. Hick, M. Lammer, H. Nabielek, J. York) 




DPR 755 

A Three-Loop Control System for the HTR Gas Turbine, (J.R. Dean, G. Soubelet) 


104





DPR 756 

Improved Methods of Measuring the Moisture Content of Gases at Sub-VPM 

Levels, (P.S. Gray, I. Gordon, N. Forsyth) 




DPR 757 

Tests on a Modified MK. X B.C.D Percipitator on the Helium Gas Cooled Dragon 

Reactor, (J.W. Leake, G.A. Barnett, P.A.A. Scott) 




DPR 758 

Dragon Operations Branch 20th Quarterly Progress Report, March 1970 May 

1970, (B.G. Chapman, W.B. Salter) 




DPR 759 

The Basic Design of a Molecular Sieve Purification Plant for the Removal of Water 

Vapour and Carbon Dioxide at Low Partial Pressures from the Helium Coolant 

Used in a High Temperature Gas Cooled Nuclear Reactor, (C. Harper, R. 

Mourareau) 




DPR 760 

Burn-up Physics for the Dragon High Temperature Reactor, (C. Hunt) 




DPR 761 to 770 





DPR 761 

Definition, Calculation and Importance of the Matrix Density in Fuel 

Consolidation, (Y. Barbier) 




DPR 762 

CREAM-7 A One Dimensional Fuel Group Burn-Up Programme with Spectrum 

Calculations, (H.R. Schober) 


105




DPR 763 

Operational Data for Charge 111, (G.D. Burholt, R. Kemmish) 





DPR 765 

FLATTER - A One Dimensional Equilibrium Fuel Managment Programme for 

Continously on On-Load Refuelled High Temperature Reactors, (J. Pedersen) 




DPR 766 

BUPO - A One Dimensional Neutron Transport Programme for Burnable Poison 

and Cell Burn-Up Calculations, (J. Pedersen) 




DPR 767 

Graphite Fuel Element Structures for High Temperature Gas Cooled Reactors, 

(J.L. Head, A.N. Kinkead) 




DPR 768 

Description of a Revised Version of the Computer Code FIPDIG, (G. Preinreich) 




DPR 769 

Studies on the Behaviour of Graphite Structures Irradiated in the Dragon 

Reactor, (M.R. Everett, L.W. Graham, F. Ridealgh) 




DPR 770 

Steady State Part-Load of HTR Gas Turbine Cycles, (G. Preinreich) 




DPR 771 to 780 





106



DPR 771 

Fission Product Release Measurements in the Dragon Reactor Cores 8 & 9 

Charge 111, (D.R. Stonier) 




DPR 772 

Dragon Operations Branch 21st Quarterly Progress Report, June 1970 Aug 

1970, (W.B. Salter) 




DPR 773 

Stereoscan Examination of Coatings from Dragon Irradiated Fuel Particles, 

(H.N.G. Wadley et al) 




DPR 774 

Carbon Dioxide Absorption on Fixed Beds of Molecular Sieves, (D.J. Barrett) 




DPR 775 

The Metrology of Coated Particle Fuel for High Temperature Reactors, (J.C. 

Hedderley) 




DPR 776 

Computer Assisted Quality Control Applied for High Temperature Reactor Fuels, 

(J.C. Hedderley) 




DPR 777 

The Fabrication of O.26 Tonne U-Content Teledial Fuel for CEGB Berkeley 

Nuclear Laboratories, (J.R.C. Gough et al) 




DPR 778 

Dragon Operations Branch 22nd Quarterly Progress Report, Sept 1970 Nov 

1970, (P.D. Capp) 




DPR 779 

107



Dragon Operations Branch Twenty-Third Quarterly Progress Report, Dec 1970 - 

March 1971, by I.K. Mason 




DPR 780 

Dragon Operations Branch 24th Progress Report, April 1971 to June 1971, I.K. 

Mason 




DPR 781 to 790 





DPR 781 

A Summary of Results on the Quality Control Testing and Inspection of Driver 

Fuel for the 3rd Charge of the Dragon Reactor Experiment, Part 3 (J.W. Wylie) 




DPR 782 

A Summary of Results on the Quality Control Testing and Inspection of Driver 

Fuel for Charge 4, Core 1 of the Dragon Reactor Experiment, (J.W. Wylie) 




DPR 783 

The HTR System and the Changing Market for Enriched Uranium, (U. Hansen) 




DPR 784 

A Designer's Approach to the Conservation of Helium in High Temperature Power 

Reactors, (G.E. Lockett, S.B. Hosegood, C. Harper) 




DPR 785 

Gas Flows in Spouting Beds, (D. Van Velzen) 




DPR 786 

Graphite Fuel Element Sleeves for High Temperature Gas Cooled Reactors, (J.L. 

Head, A.N. Kinkead) 


108





DPR 787 

The Techniques Used in the Dragon Project to Measure the Fission Product 

Release Performance of High Temperature Reactor Fuel, (J. York et al) 




DPR 788 

Manufacture of Driver Fuel for the Dragon Rector with Kernels Obtained by the 

Gel supported Precipation Process, (A.G. Faccini et al) 




DPR 789 

Safety Aspects of High Temperature Reactor Systems 




DPR 790 

A Survey of Pyrocarbon and Silicon Carbide Coating in a 3 inch Diameter 

Column, (J.P. Thomas) 




DPR 791 to 800 





DPR 791 

Statistical Irradiation Studies on Dragon Le Series Coated Fuel Particles, (H.T. 

Baker, P.E. Brown, J.H. Evans) 




DPR 792 

Reactivity Calibration of Control Rods, (C. Hunt, J.C. Stillwell) 




DPR 793 

Advances in the Pyrocarbon Coating of Fuel Particles, (D.N. Lamb, E.H. Voice) 




109



DPR 794 

The Role of Irradiation Experiments in the Development of High Temperature 

Reactors, (P.Barr et al) 




DPR 795 

An Examination of Fuel and Graphite Temperatures in 2-Dimensional Cross- 

Sectional Configurations of Fuel Elements, (A.N. Kinkead, Y. Paternot) 




DPR 796 

The Stress-Strain Characteristics of Non-Irradiated and Irradiated Nuclear 

Graphites, (M.R. Everett, F. Ridealgh) 




DPR 797 

The Selection and Characterising of a Resin for HTR Fuel Matrix Fabrication, 

(E.W. Orwell, E.H. Voice, D.W. Sturge) 




DPR 798 

Behaviour of Small Leaks in Mild Steel Boiler Tubes when Subject to Water at 

2,500 PSIG and 350 Degrees Celsius, (C. Harper, I.M. Coe, A.L. F. Stringer) 




DPR 799 

Tritium Production and Distribution in High Temperature Gas Cooled Reactors, 

(N. Forsyth) 




DPR 800 

The Choice of Pyrocarbon Deposition Agent for Nuclear Fuel Particles, ( R.L.R. 

Lefevre, et al) 




DPR 801 to 810 





DPR 801 

110



Dragon Operations Branch 25th Quarterly Progress Report July - Sept. 1971, 

(I.K. Mason) 




DPR 802 

Dragon Operations Branch 26th Quarterly Progress Report Oct. - Dec. 1971, (I.K. 

Mason) 




DPR 803 

HTR Fuels and Their Future Development, (L.W. Graham, M.S.T. Price) 




DPR 804 

Users Manual for Programme TACOR - A Fortran IV Computer Programme for the 

Thermal Analysis of Composite Regions, (L.E. Hulbert, A.T. Hopper) 




DPR 805 

The Diffusion of Strontium and Caesium in Pyroltyic Silicon Carbide, (B. 

Chinaglia) 




DPR 806 

Dragon Reactor Opeating Experience, (B.G. Chapman) 




DPR 807 

A Basis Process Design Study for the Fine Purification of Helium Coolant Used in 

HTGC Reactors, (R. Mourareau) 




DPR 808 

HTR Fuel Element Technology, (L.W. Graham, M.S.T. Price) 




DPR 809 

The Two-Phase Diffusion Model, (H. Walther, P.G. Novaris) 



111




DPR 810 

The Influence of Control ROD Patterns on the 3-Dimensional Power Distributions 

in the Dragon Reactor, (C. Hunt, R.M. James) 




DPR 811 to 820 





DPR 811 

KPD Present Worth Fuel Cycle Calculation Methods and Codes, (U. Hansen) 




DPR 812 

Reactor Containmnet: Preliminary Considerations for the HTR System, (R. Del 

Beccars, G. Mancini) 




DPR 813 

Post-Irradiation Evaluation of Dragon Second Metallurgical Series Experiments 

(F.E's 311, 474,477)(M.R. Everett, W. Krischer) 




DPR 814 

The MUPO Nuclear Data Library 5,(L. Massimo, W. Giesser, G. Mancini) 




DPR 815 

Addendum to Users Manual for Programme TACOR, (J.C. UHRY) 




DPR 816 

Interim Report on the Behaviour of Reactor Group UKAEA Compatability 

Specimens Exposed in Dragon Heat Exchangers, (H.C. Cowen et al) 




DPR 817 

112



Experience Gained in the Dragon Project with the SNAM Process of Kernel 

Manufacture for HTR Fuels, (A. Facchini et al) 




DPR 818 

The Status of Fuels and Metals for High Temperature Gas Cooled Reactors,(L.W. 

Graham, R.A.U Huddle, M.S.T. Price) 




DPR 819 

COLIBRI HTR 3 - An Advanced Fuel Coating Irradiation, (E.H. Voice, Y. Barbier, 

D.W. Sturge) 




DPR 820 

Zero Energy Experiments on the Dragon Reactor Prior to Charge IV Start Up , 

(V.E. Della Loggia, C. Hunt, W.H. Taylor) 




DPR 821 to 830 





DPR 821 

Temperature Coefficients for a Prismate Type On-load Repelled H.T.R. with Lowenriched 

Uranium Fuel (R. Hansen) 




DPR 822 

DELPCO - A Computer Programme for Calculation of Reactor Pressure Drop (J.C. 

Uhry) 




DPR 823 

Thermal/Structure Evaluation a Tubular Interacting Fuel Pin End Regions (A.N. 

Kinkead) 




DPR 824 

113



Irradiation Experiments Marked by the Dragon Project to Test H.T.R. Fuel under 

Abnormal Conditions (P. Barr) 




DPR 825 

The 'CURVO' Programme (B.G. Pitchford) 




DPR 826 

Hassan - A Complete Programme for Thermal and Structural Analysis of 

Prismatic H.T.R. Fuel Elements 




DPR 827 

Cocsix - A Complete Programme for Thermal Calulations of Fuel Elements in 

Circular Symmetry (J.C. Uhry) 




DPR 828 

Performance Limits of Coated Particle Fuel (L.W. Graham, I.D. Hick) 




DPR 829 

Fisson Product Release Measurements in the Dragon Reactor (D.R. Stonier) 




DPR 830 

Analogue Computer Studies of the Control Dynamics of a 600 MW(e) HTR - 

Helium Turbine Plant (G. Flewing, J.R. Dean, G. Soubelet) 




DPR 831 to 840 





DPR 831 

Dragon Operations Branch 27th Quaterly Progress Request, January March 

1972 



114




DPR 832 

The Irradiation Behaviour of HTR Fuel Components (M.R. Everett, R. Blackstone) 




DPR 833 

Corrosion Experiments on Irradiated Dragon Fuel Components 




DPR 834 

Dragon Charge 18 - Report on Irradiation Conditions and Fission Product 

Release Measurements (P. Svensson) 




DPR 835 

A Simplified Method of Restrained Distortion Assessment of Reactor Core 

Components (B.E. Pitchford, A.N. Kinkead) 




DPR 836 

Dragon Operations Branch 28 Quaterly Progress Report, April - June 1972 (I.K. 

Mason) 




DPR 837 

Status of Model Describing the Mechanical Performance of Coat Particle Fuels (H. 

Hick) 




DPR 838 

Post-irradiation Exam Results Driver Pins os Charge with a Particular Reference 

to Corrosion and Bowing (W. Krische, K. Mayer) 




DPR 839 

Structoral Evaluations of Components in the High Temperature Reactor Core (J.L. 

Head, A.N. Kinkead) 



115




DPR 840 

Exaimination of the Fission Gas Releases from the Experiments FPC 2, 3 & 10 in 

Charge IV of the Dragon Reactor (J. Steephead, K. Upperon) 




DPR 841 to 850 





DPR 841 

Boron Carbide Particle Irradiation in the Dragon Reactor (C.F. Walldets) 




DPR 842 

Pyrolytic Carbon Coated Particles Deposited from Propylene in a Fluidized Bed 

(J.P. Thomas, A.C. Beddals) 




DPR 843 

Porus Coatings Deposited from Acetylene in a 3 Inch Fluidized Bed (J.P. Thomas, 

A.C. Beddals) 




DPR 844 

Colibri HTR 3, An Advanced Fuel Coating Irradiation (E.H. Voice) 




DPR 845 

The Significance of Gas Pressure Build-up in Coated Particles (M. Wagner- 

Coppler) 




DPR 846 

Methods of Inspection and Testing of HTR Fuels (J. Hollinay et al) 




DPR 847 

The Thermal and Mechanical Performance of H.T.R Fuel Elements (A. N. 

Kinkead) 

116






DPR 848 

Ci-Play - A One-dimensional Digital Computer Programme for Thermal and 

Neutron Kinetics of HTR Fuel Channels (G. Soubelet, J.R. Dean, D.V. Kissey) 




DPR 849 

Comparison Between Measurement Predictions Experiments Irradiated in 

Dragon Core Charge IV and Up-to-date Thermal Performance for Driver Fuel 

Elements (M.J. Waldravens) 




DPR 850 

Performance Limits of Coated Particle Fuel (L.W. Graham, H. Hick) 




DPR 851 to 860 





DPR 851 

Quality Management of HTR Fuels (J.P. Audenbeam) 




DPR 852 

The Irradiation Behaviour of HTR Graphites (M.R. Everett) 




DPR 853 

Determination of Fission and Reaction Gases in Coated Fuel Particles (A. Shligh, 

H. Bildstein) 




DPR 854 

Determination of Free Volumes in Coated Fuel Particles (A. Shligh, H. Bildstein) 



117




DPR 855 

The Idea of Pyrocarbon Fuel Particle Coatings at High Fast Neutron Doss (J.C. 

Janvier, C. Moreau) 




DPR 856 

The Permeability of Silicon Carbide Coatings to Fission Products (E. H.Voice et al) 




DPR 857 

The Predictions of Fission Product Behaviour in HTR's (G.G Nastri, P.R Rowland) 




DPR 858 

A Review of HTR Graphite Corrosion (F.P.O. Ashworth et al) 




DPR 859 

The Calcualtion of Co-pressures in Oxine Coated Particle Fuel by the Molybidate 

Model (M. Wagner-Zoppler) 




DPR 860 

The Dragon Metals Creep Corrosion Test Programme at CIIR Oslo (H.G.A. Baden) 




DPR 861 to 870 





DPR 861 

A Re-evaluation of the Armoes Behaviour of UO, Coated Particle Fuel 




DPR 862 

Fuel Management Strategies for the Low Enriched 600 MW (e) Dragon HHT 

Reactor (Hansen) 



118




DPR 863 

A Data Information System for Graphite Materials for HTR's Management 

(Electronic Data Processing) 




DPR 864 

The Feasability fo the Reactor Emission Method for Testing the Fission Gas 

Leakage of Unirradiated Coated Particle Fuel (R.E. Siddall) 




DPR 865 

The Safety of Operations in the Dragon Fuel Element Fabrication Laboratory 

from 1968-1972 inclusive (E.N. Bachelor) 




DPR 866 

Results from Some Recent Fuel Coating Irradiations (E.H. Voice) 




DPR 867 

Advances in HTR Fuel Matrix Technology (E.H. Voice) 




DPR 868 

Mass Transfer in Helical Bulk of Tubes - Subroutine HCOH (C. Leuthrob) 




DPR 869 

A WIMS-E Analysis of the Zero Energy Experiments on Dragon Project to Charge 

IV (M.J. Lancefield) 




DPR 870 

Reactivity Accidents in a 1,500 MW (th) HTR (W. Doboesky) 




DPR 871 to 880 

119






DPR 871 

Thermal and Stress Analysis on a Multi-hole Graphite Test Block (I.T Cords) 





DPR 872 

Fuel Consolidation the Characteristics of Long Compacts Manufactured by 

Transversat Pressing (J.P. Thomas) 




DPR 873 

Some Considerations of System Generators for High Temperature Gas Cooled 

Reactors (L.W. Graham) 




DPR 874 

Metallic Fission Product Behaviour in Dragon Fuel Elements as Observed from 

Gamma - Spectometre Examination 




DPR 875 

Mass Spectrometric Determination Through Molecular Beam of CO, CO2, Xe, Cs, 

Kf Pressures at High Temperature in Irradiated Coated Particles with Oxide 

Kernels (A. Partoned) 




DPR 876 

Irradiated Performance of HTR Fuel Compacts (M.R. Everett) 




DPR 877 

Irradiated Performance and Selective Graphites for HTR's (M.R. Everett) 




DPR 878 

Colibri HTR4 Irradiation Experiement in OSIRIS : Objective, Fuel Manufacture, 

Pre-irradiation Evaluation and Nominal Conditions of Irradiation (Y. Barbier et al) 


120




DPR 879 

Dragon Project Scandinavian Information Meeting RIso 





DPR 880 

The Irradiation of Special Coated Particles Designed to Test Stress-Model 

Calculated Predictions (M.R. Everett, L.W. Graham, H. Walker) 




DPR 881 to 890 





DPR 881 

A Parametric Survey of the Depressurisation Accident Followed by a Boiler Tube 

Burst in a HTR System 




DPR 882 

Irradiation Experiment Studsvik (T.C. Steemans) 




DPR 883 

Alternative Fuel Cycles for HTGR's (H. Gutmann) 




DPR 884 

Operational and Mantainence Expertise with the Dragon Reactor Experiment 

(R.G. Chapman) 




DPR 885 

HTR Fuel Development and Testing in the Dragon Project 




DPR 886 

121



Status of Graphite Technology and Requirements for HTGR's (G. Bengal, M.R. 

Everett, W.P. Eatherly) 




DPR 887 

Gas Cooled Reactor Safety Technology (F.P.O. Ashworth, J.H. Bowen, J. Kirk) 




DPR 888 

Fatigue Testing of Isotropic Gilsocauben Graphite (M. Gateau, G. Sertou at al) 




DPR 889 

Installation and Initial Performance of Experimental Direct Lines (R.F. McIver, 

R.O. Sage, R. Simon, C. Harper) 




DPR 890 

The Design and Development of Thermal Insulation for High Temperature Gas 

Cooled Reactors (S.B. Hosegood, I.D. Jones) 




DPR 891 to 900 





DPR 891 

Dragon Reactor Primary Coolant Circuit : Circuit kinetics Based on Argon 

Injections (A.R. Trowell) 




DPR 892 

Stragt - A Two Material Version of the STAG Code Embodying Wigner 

Improvements (A.N. Kinkead) 




DPR 893 

Fission Product Release Measurements in the Dragon Reactor Codes IV and V 

Charge IV (D.R. Stonier) 


122





DPR 894 

STG - Stress in Transversly Isotropic Graphite Two-dimensional Two-material 

Code Embodying Rotational Plane State as an Option 




DPR 895 

Potential Industrial Applications of High Grade Process Heat from a High 

Temperature Gas Cooled Nuclear Reactor (Humphries and Glasgow) 




DPR 896 

Development of Very High Temperature Reactors to Process Heat Supply 




DPR 897 

Am Experiment to Study the Influence of HTR helium Environments on the 

Structure and Mechanical Properties of Primary Circuit Materials (L.J. Hankart) 




DPR 898 

HTR Fuel Development for Advanced Applications (H. Nickel et al) 




DPR 899 

Plutonium in High Temperature Reactors (U. Hansen) 




DPR 900 

A Model of Pyrocarbon and its Deposition Mechanism Based on the Results 

Obtained in Semi-industrial Scale Coating Furnaces (R.L. Lefevre) 




DPR 901 to 910 





123



DPR 901 

Coated Particle Fuel for the High Temperature Gas Cooled Reactors The Coating 

Process (J.P. Thomas et al) 




DPR 902 

Mechanisms of Fission Product Migration in Nuclear Graphite (P.R. Towland) 




DPR 903 

Alloy 800 and its Properties in HTR Atmospheres (W. Betteridge, H.G.S. Bates) 




DPR 904 

A WIMS Analysis of the Zero Energy Experiments Performed on the Dragon 

Reactor 




DPR 905 

Tritium Production and Distribution in High Temperature Gas Cooled Reactors 

Tritium Generation, Retention, Distribution and Environmental Release in a 

Rotional 1,500 MW(th) HTR (N. Forsyth) 




DPR 906 

Status of Nuclear Process Heat Development Work in the Dragon Project (S.B. 

Hosegood) 




DPR 907 

Sorption and Diffusion of Caesium in some Nuclear Graphites (B. McEnarey, R.O. 

McHean) 




DPR 908 

Graphite and Matrix Materials for very High Temperature Reactors 




DPR 909 

124



Reactor Evaluation : Fission Product Gas Release from Dragon Reactor Core 

Charge IV (Cores 3&4), Charge V (Cores 1, 2 &3) 




DPR 910 

Statistical Irradiation Studies on Dragon L.E Series Coated Fuel Particles Part II - 

Radiochemical Results (H.T. Baker, P.E. Brown et al) 




DPR 911 to 920 





DPR 911 

Theoretical Calculations of Fast Flux and Graphite Damage Reaction in the 

Dragon Reactor 

(C. Hunt) 




DPR 912 

Radiation Induced EMF Developing in the Insulation of Metals and Leather 

Mineral Insulated High Temperature Thermocouple and its Effects on the 

Thermocouple Signal (S. Tarassenko) 




DPR 913 

Preliminary Investigation into the Cause of Helium Leakage from Stainless Steel 

Pipework in Dragon Reactor (J.D. Frampton, J. Holliday) 




DPR 914 

Experiments to Study the Effects of Interaction of HTR Helium with Metals, 

Alloys and Ceramics (L.J. Hankart, k. Mayr) 




DPR 915 

The VSOP System Present Work Fuel Cycle Calculation Methods and Codes KPD 

(H. Hansen) 




125



DPR 918 

The Development of the Flip-flop Coolant Control Valve Rib Behaviour in Air (T. 

Schmeskal) 




DPR 919 

Summary of a Round Table Discussion on Amoeba Mechanisms in Oxine Fuel 

Particles (H. Hick) 




DPR 920 

Thermal and Stress Analysis on the Moulded Block Experiments (H. Cords et al) 




DPR 921 to 930 





DPR 921 

The Low-enriched Uranium and the Th/U Cycles in the GA 1,160 MW(th) High 

Temperature Reactor 




DPR 922 

The Post-irradiation Measurement of Noble Fission Gas Release from the Charge 

III Low-enriched VO2 Centre Rod Experiments (P.D. Good, P.G.R. Giles) 




DPR 923 

Colibri HTR 3, An Advanced Fuel Coating Irradiation 

Corail VII - An Associated Fast Neutron DO2 Experiment (E.H. Voice) 




DPR 925 

Reactor Phusics Measurements on the Zerp Energy HTR Lathre HITREX - 1 at 

CEGB Berkeley Nuclear Laboratories (V.E. Della-Loggia) 




DPR 926 

126



A Study of the High Temperature Corrosion of Iron-Nickel-Chronium Alloys by 

Low Analysis (W. Betteridge, D. Quataert) 




DPR 927 

Fuel Development for Advanced HTR Systems (L.W. Graham et al) 




DPR 928 

Post-irradiation Examination of FE 433 (23C) (J.H. Evans, D.H. Carter, K. Mayr, 

H. Nabielek) 




DPR 929 

Post-irradiation Examination of Colbri HTR - 2 (K. Mayr et al) 




DPR 930 

The Dragon Project Environmental Creep Corrosion Test Facility at CRL, FIAT (C. 

Eastes et al) 




DPR 931 to 940 





DPR 931 

Initial Tests on the Environmental Creep Rigs at FIAT (S. Quaranta, H. Wather) 




DPR 932 

Helium Imputiry Levels for Compatibility Testing of HTR Primary Circuit 

Materials (M.R. Everett) 




DPR 933 

The Programme for Environmental Creep Testing of Primary Circuit Materials at 

CRL, FIAT 



127




DPR 934 

The Influence of Impure Helium on Properties of Some Austenitic Steel (H.G.A. 

Bates et al) 




DPR 935 

On the Future Development of Experimental and Theoretical Techniques in the 

Dragon Project Metals Programme at CLR, FIAT (H. Walther) 




DPR 936 

Use of Air Gauging Methods in Pie Work on Dragon Fuel Elements (F. Mayer) 




DPR 937 

The Irradiation Behaviour of Plutonium Coated Particle Fuel inthe Dragon Reator 

Experiment (G. Foimann, K. Mayr, J. York, P.E. Brown, J.H. Evans) 




DPR 938 

Method of Pressure Drop Evaluation in Turbulent Flow Applied to Dragon Reactor 

(F.A. Dolciami) 




DPR 939 

Build up of Transurmanium Nuctiles in High Temperature Reactors (U. Elowssen) 




DPR 940 

Nestor Analysis with Dragon Methods (V.E. Della Loggia, G. Schleser, F. Woolsh) 




DPR 941 to 950 





DPR 941 

128



Rotational Plane Strain and its Application in Two-Dimensional Finite Element 

Analysis, A.N. Kinkead 




DPR 942 

Control Road Repres with Linked Transport and Diffusion Through Methods, 

(H.J. Neef) 




DPR 943 

A Graphite Damage Calibration Experiment in the Dragon Reactor, (M.R. Everett) 




DPR 945 

The Examination of an Articulated Dragon Reactor Control Rod, (K. Mayr, L.J. 

Hankart) 




DPR 946 

HRT Direct Helium Gas Turbine Cycle Combined with Other Cycles, (G. 

Johansson) 




DPR 947 

The Measurement of Condensable Fission Products in the Dragon Reactor 

Coolant from Core 8, Charge 111, to Core 4, Charge V, (G.A. Barnett, N. Forsyth, 

D.R. Stonier) 




DPR 948 

A VHTR Coating Irradiation part 1, Principles and Preparation, (E.H. Voice, M. 

Wagner - Löffler, R. Haange, R.C. Burnett, D.R Smith, T.T. Keystone) 




DPR 949 

A Thermal Analysis Method for the Evaluation of Radial Temperature 

Distributions in Fuel Channels with Thermal Interconnection through Parallel 

Coolant Channels the "Cocktail N' Computer" Code, (F.A. Dolciami) 




129



DPR 950 

Preliminary Orientation and Parametric Survey for very High Temperature 

Reactors with Intermediate Heat Exchanges 




DPR 951 to 960 





DPR 951 

Operational Experience with the Dragon Reactor Experiment of Relevance to 

Commercial Reactors, (R.D. Capp) 




DPR 956 

The Status of Information Required for an Independent Analysis of Risks 

Associated with HTR, (F.P.D. Ashworth, H.J. de Nordwall) 




DPR 957 

Some Aspects fo the Kinetics of the Attainment of CO Equilibrium in Oxide HTR 

Fuel Particles, (A. Strigl, E. Proksch) 




DPR 958 

A Pseudo-3-D Sheady State Aerothermal Analysis of a Multi-Fuel Region Multi- 

Coolant Channel Prismatic Core Section Sector Using the Finite Element Method 

the "Cedrazal" Computer Code, (F.A. Dolciami) 




DPR 960 

Optim-A Matrix Band-Width Optimisation Programme, (M. Huarl) 




DPR 961 to 970 




Item: DRA-298.961 10/1975 - 1976 

DPR 961 

Summary of Pressure Chop Tests on Reactor Components in Air, (T. Schmeskal) 

130






DPR 962 

DIDO 919/8 A HTR Fuel Particles Experiment in which Kernel Oxygan Gelters 

are Evaluated, (T.C. Steemers) 




DPR 963 

HTR Plant Kinetics Models, (J.R. Dean, G. Johansson, P.C. Kingdom) 




DPR 964 

High Temperature Gas-Cooled Reactor Safety, (F.P.O Ashworth, H.J. de 

Nordwall) 




DPR 965 

Preliminary Investigations into the Compatability of Ceramics with HTR Helium 

in the Dragon Reactor, (ACE 2), (L.J. Hankart, K. Mayr, G. Worrall) 




DPR 966 

EIR/Dragon Plated-out Samples Experiment Part 1, Operational Data During 

Charge V, and First Results for Sample Carriers, 1 and 2 , (H.F. Mollet, G.A. 

Barnett, D. Barnes) 




DPR 967 

Cerous Oxide as an Oxygen Getter in HTR Fuel, (T.C. Steemers) 




DPR 968 

A Review of the Results of the High Temperature Irradiation Creep Experiments 

on Graphites for HTR Applications, (H.J. Veringa, R. Balckstone) 




DPR 970 

Behaviour of Materials for Advanced High Temperature Reactors, (R. H. Cook, 

D.F. Luphon, H.G.A. Bates) 


131




DPR 971 to 981 






DPR 971 

The Dragon Reactor as a Test Facility for Circuit Materials Past, Present and 

Future, (M.R. Warren) 




DPR 974 

Carbon Diffusion in Basic Austenitic Steels, (O. Demel, E. Keil, P. Kostecki) 




DPR 978 

Stigma-Stress in Transversly Isotropic Graphite Made Aei-Symmetrically, (A.N. 

Kinkead, A.L. Colville) 




DPR 979 

The Colibri HTR 4 Fuel Irradiation, Part 11 - First Results, (D. I. Smith, E.H. 

Voice) 




DPR 980 

Compatability Tests of High Temperature Primary Circuit Materials in the Dragon 

Reactor (MK.111,Head Exchanger Basket) (K. Mayr, L.J. Hankart, M.R. Warren) 




DPR 981 

Helical Coil Intermediate heat Exchanges for Very High Temperature Reactors, 

(R.F. McIver) 



DRA.B-MPS Monthly Progress Statement 

1962 

Information on the progress in the Research and Development and in the engineering 

works in the different main areas, i. e. design, manufacture, site erection and tests, and 

132



on the time schedule, prepared by the Dragon Project Office and distributed to all 

Members of the Board of Management and General Purposes Committee. 


DPMPS(62)1 to 9 



DPMPS(63)10 to 23 



DPMPS(64)22 to 33 



DPMPS(65)34 to 45 



DPMPS(66)46 to 57 



DPMPS(67)58 to 69 



DPMPS(68)70 to 81 



DPMPS(69)82 to 93 



DPMPS(70)94 to 105 



DPMPS(71)106 


DRA.B-OP Progress Reports 

1962 

Reports from the Dragon Operations Group, named after 1973 Dragon Operations 

Branch. 


DPROG 1 to 23 



DPROG 25 to 42 

133






PR(65)3 to 12 




PR(66)1 to 12 




PR(67)1 to 12 




PR(68)1 to 12 




PR(69)1 to 12 




PR(70)1 to 12 



PR(70)1 to 12 



PR(72)1 to 12 



PR(73)1 to 12 



PR(74)1 to 12 



PR(75)1 to 12 




134



DRA.C Research & Development and Engineering 

1962-1975 

Under this title were grouped the series of technical documents produced by diferent organs and 

committes within the Dragon Project. Documents are identified by specific codes and arranged in a 

numeric sequence. Most of them include technical specifications that include draws, graphics, 

photographs,ecc. 

DRA.C-AD Assessment Documents 

1964-1969 

15 files 

Documents coded DPAD 1 to 149. Technical documents concerning studies and analysis 

upon problems found in the Drago Project. 


DPAD 1 to 10 



DPAD 11 to 20 



DPAD 21 to 30 



DPAD 31 to 40 



DPAD 41 to 50 



DPAD 51 to 60 



DPAD 61 to 70 



DPAD 71 to 80 



DPAD 81 to 90 



DPAD 91 to 100 


135


DPAD 101 to 110 



DPAD 111 to 120 



DPAD 121 to 130 



DPAD 131 to 140 



DPAD 141 to 149 




DRA.C-FID Fuel Irradiation Dossier 

1971 

Documents coded FID 1 to 98 mentioning "Project Staff Use Only". They respect to 

studies on fuel. 


FID 1 to 3 



FID 5 to 9 



FID 10 to 18 



FID 19 to 23 



FID 24 to 28 



FID 29 to 30 



FID 39 to 40 


136


FID 41 to 50 



FID 51 to 60 



FID 61 to 71 



FID 72 to 81 



FID 82 to 98 


File: DRA-95 

FID DX 

Docs. coded FID DX 

in course of treatment 


File: DRA-96 

FID DX 

Docs. coded FID DX 

in course of treatment 




DRA.C-ID Irradiation Documents 

1969-1975 

40 files 

Documents coded DPID 1 to 798. Technical matters concerning control and safety of the 

reactor. 


DPID 1 to 20 



DPID 21 to 40 



DPID 41 to 60 



DPID 61 to 80 


137


DPID 81 to 100 



DPID 101 to 120 



DPID 121 to 140 



DPID 141 to 160 



DPID 161 to 180 



DPID 181 to 200 



DPID 201 to 220 



DPID 221 to 240 



DPID 241 to 260 



DPID 261 to 280 



DPID 281 to 300 



DPID 301 to 320 



DPID 321 to 340 



DPID 341 to 360 




138


DPID 361 to 380 



DPID 381 to 400 



DPID 401 to 420 



DPID 421 to 440 



DPID 441 to 460 



DPID 461 to 480 



DPID 481 to 500 



DPID 501 to 520 



DPID 521 to 540 



DPID 541 to 560 



DPID 561 to 580 



DPID 581 to 600 



DPID 601 to 620 





139

DPID 621 to 640 



DPID 641 to 660 



DPID 661 to 680 



DPID 681 to 700 



DPID 701 to 720 



DPID 721 to 740 



DPID 741 to 760 



DPID 761 to 780 



DPID 781 to 798 


DRA.C-PAT Patent specifications 

1959 

Docs. coded DPPS 1 to 222. 


DPPS 1 to 50 



DPPS 51 to 100 



DPPS 101 to 150 



DPPS 151 to 200 




140


DPPS 201 to 222 




DRA.C-PS Project Specifications 

1961 

Dragon Project Specifications, numbered 1 to n. There are many documents missed. 

Files were organized in order to include 10 documents each. 


DPS 1 to 10 



DPS 11 to 20 



DPS 21 to 30 



DPS 31 to 40 



DPS 41 to 50 



DPS 51 to 60 



DPS 61 to 70 



DPS 71 to 80 



DPS 81 to 90 



DPS 91 to 100 



DPS 102 to 104 


141



DRA.C-RDD Research and Development Division 

1960-1975 

46 files 

Documents coded DPRDD 1 to 1870 for "Official Use Only" or "Project Staff Use Only". 


DPRDD 1 to 50 



DPRDD 51 to 100 
































142























DPRDD 951 to 1000 



DPRDD 1001 to 1010 



DPRDD 1011 to 1050 



DPRDD 1051 to 1100 



DPRDD 1101 to 1150 



DPRDD 1151 to 1200 





143

DPRDD 1201 to 1250 



DPRDD 1251 to 1270 



DPRDD 1271 to 1300 



DPRDD 1301 to 1350 



DPRDD 1351 to 1400 



DPRDD 1401 to 1450 



DPRDD 1451 to 1475 



DPRDD 1476 to 1500 



DPRDD 1501 to 1550 



DPRDD 1551 to 1575 



DPRDD 1576 to 1600 



DPRDD 1600 to 1630 



DPRDD 1631 to 1650 



DPRDD 1651 to 1700 




144


DPRDD 1701 to 1720 



DPRDD 1721 to 1750 



DPRDD 1751 to 1780 



DPRDD 1780 to 1800 



DPRDD 1801 to 1820 



DPRDD 1821 to 1840 



DPRDD 1840 to 1870 


DRA.D Physics Meetings 

1973-1975 

Papers presented at 16. to 20. Dragon Countries Physics Meetings 


01 - 16. Meeting 

March 1973 




September 1973 




March 1974 




September 1974 




May 1975 



145




146

DRA Dragon Project - European University Institute

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