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absolute values of proton spectra. The composite particles are also not correctly reproduced. FLUKA is giving a good total cross-section value thanks to differences cancelling each other at forward and backward angles. Further comparisons with theoretical approach are underway especially with model including pre-equilibrium emission such as MINGUS [10]. Other data on lead using proton-induced reactions at the same energy beam are under analysis and will be delivered soon to enrich the data tables. This work has been supported by the European Commission under the concerted action N o FI4I- CT98-0017 and by the GDR GEDEON (research group CEA – CNRS – EdF – FRAMATOME). REFERENCES [1] A. Bol, P. Leleux, P. Lipnik, P. Macq and A. Ninane, A Novel Design for a Fast Neutron Beam, NIM, 1983, 214, 169-173. [2] I. Slypen, V. Corcalciuc and J.P. Meulders, Geometry and Energy Loss Features of Charged Particle Production in Fast-neutron Induced Reactions, NIMB, 1994, 88, 275-281. [3] I. Slypen, V. Corcalciuc and J.P. Meulders, Proton and Deuteron Production in Neutron-induced Reactions on Carbon at E n = 42.5, 62.7 and 72.8 MeV, Phys. Rev. C, 1985, 51, 1303-1311. [4] S. Benck, I. Slypen, V. Corcalciuc and J.P. Meulders, Light Charged Particle Emission Induced by Neutrons with Energies Between 25 and 65 Mev on Oxygen I. Protons and Deuterons, Eur. Phys. J. A., 1998, 3,149-157. [5] GEANT: Detector Description and Simulation Tool, CERN program library long write-up W5013. [6] C. Kalbach, Systematic of Continuum Angular Distributions: Extensions to Higher Energies, Phys. Rev. C, 1988, 37, 2350-2370. [7] F.E. Bertrand and R.W. Peele, Complete Hydrogen and Helium Particle Spectra from 30 to 60 Mev Proton Bombardment of Nuclei With A = 12 to 209 and Comparison with the Intranuclear Cascade Model, Phys. Rev. C, 1973, 8, 1045-1064. [8] International Commission on Radiation Units and Measurements, Nuclear Data for Neutron and Proton Radiotherapy and for Radiation Protection, reports 63, 1999. [9] A. Ferrari and P.R. Sala, A New Model for Hadronic Interaction at Intermediate Energies for the FLUKA Code, The MC93 international conference on Monte Carlo Simulation in High Energy and Nuclear Physics, Tallahassee, Florida, 1993, 277-288, World scientific, Singapore. [10] A.J. Koning, M.B. Chadwick, Microscopic Two-component Multistep Direct Theory for Continuum Nuclear Reactions, Phys. Rev. C, 1997, 56, 970-99. 770
HIGH AND INTERMEDIATE ENERGY NUCLEAR DATA FOR ACCELERATOR DRIVEN SYSTEMS – THE HINDAS PROJECT J.P. Meulders 1 , H. Beijers 2 , J. Benlliure 3 , O. Bersillon 4 , J. Cugnon 5 , Ph. Eudes 6 , D. Filges 7 , A. Koning 8 , J.F. Lecolley 9 , S. Leray 10 , R. Michel 11 , N. Olsson 12 , K.H. Schmidt 13 , H. Schuhmacher 14 , I. Slypen 1 , H. Synal 15 , R. Weinreich 16 1 Institut de Physique Nucléaire, Université Catholique de Louvain, 1348 Louvain-la-Neuve, Belgium 2 Kernfysich Versneller Instituut, Rijksuniversiteit Groningen, 9747 Groningen, The Netherlands 3 University of Santiago de Compostela, 15706 Santiago de Compostela, Spain 4 CEA-Bruyères-le-Châtel, Service de Physique Nucléaire, 91680 Bruyères-le-Châtel, France 5 Institut de Physique B5, Université de Liège, 4000 Sart Tilman Liège 1, Belgium 6 Subatech, Université de Nantes, Ecole des Mines de Nantes, IN2P3-CNRS, 44307 Nantes, France 7 Forschungszentrum Jülich GmbH, Institut für Kernphysik, 52425 Jülich, Germany 8 Nuclear Research and Consultancy Group, 1755 Petten, The Netherlands 9 Laboratoire de Physique Corpusculaire de Caen, IN2P3-CNRS/ISMRa et Université de Caen, 14050 Caen, France 10 DAPNIA/SPhN CEA/Saclay, 91191 Gif-sur-Yvette, France 11 Zentrum für Strahlenschutz und Radioökologie, Universität Hanover, 30167 Hanover, Germany 12 Department of Neutron Research, Uppsala University, 75121 Uppsala, Sweden 13 Gesellschaft für Schwerionenforschung mbH, 64291 Darmstadt, Germany 14 Physikalisch Technische Bundensanstalt, 38116 Braunschweig, Germany 15 Institute of Particle Physics, ETHZ, 8093 Zurich, Switzerland 16 Paul Scherrer Institute, 5232 Villingen-PSI, Switzerland Abstract The HINDAS project (High and Intermediate energy Nuclear Data for Accelerator driven Systems) is a three years project supported by the European Commission under the Fifth Framework Program. The gathering of 16 partners, both experimentalists as theoreticians, allows to measure the wealth of new nuclear reaction cross-sections in the energy range between 20 MeV and 2 GeV on 3 elements of crucial importance for ADS systems: Pb as a target element, U as an actinide and Fe as a shielding element. The new experimental data will help to benchmark the existing theoretical models or to improve them. The assembly of nuclear data tables on those elements will allow interpolating to other elements appearing to be important in the design and the construction of an European ADS demonstrator. 771
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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
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SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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Figure 1. The natural convection im
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Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
Page 522 and 523:
1. Introduction Research and develo
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Table 2. Core design parameters for
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2.2 Representation of MA transmutat
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Figure 1(b) shows the cases for the
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It is found that the higher MA tran
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REFERENCES [1] T. Ikegami, H. Hayas
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1. Introduction The management of t
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Table 1. Core performance of MA and
Page 538 and 539:
Figure 3. Nuclear electricity capac
Page 540 and 541:
Table 3. Experimental items at PEF
Page 542 and 543:
REFERENCES [1] Takano H., Akie H.,
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1. Introduction and background The
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neutron source, the reactor can mai
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atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
Page 552 and 553:
A possible way to maintain the k ef
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higher than 99% of 239 Pu, and high
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TRANSMUTATION OF NUCLEAR WASTES WIT
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Figure 1. PBT conceptual view Table
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very tight holders for fission frag
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5. Cooling system A preliminary des
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spectral densities [10,11] and can
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MYRRHA, A MULTI-PURPOSE ADS FOR R&D
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hexagonal assemblies of 122 mm plat
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to achieve the requested performanc
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3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
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• Industrial partners, in particu
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1. Introduction The transmutation o
Page 582 and 583:
Existing accelerators have been des
Page 584 and 585:
suggested to look for an innovative
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Table 1. Main lead-bismuth eutectic
Page 588 and 589:
4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
Page 595 and 596:
of its potential use in nuclear wea
Page 597 and 598:
Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
Page 603 and 604:
in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
Page 607 and 608:
Figure 13. Elevation AD-FMHR The fa
Page 609:
Deep burn-up of 239 Pu and fissiona
Page 613:
POSTER SESSION PARTITIONING M.J. Hu
Page 616 and 617:
1. Introduction The study of the be
Page 618 and 619:
Plutonium was simulated with the no
Page 620 and 621:
The influence of uranium and pluton
Page 622 and 623:
The influence of uranium and pluton
Page 624 and 625:
REFERENCES [1] I.I. Nazarenko, A.M.
Page 626 and 627:
1. Introduction The long-term radio
Page 628 and 629:
Ce Ce 3+ Cl - Cl 2 The voltammogram
Page 630 and 631:
Figure 3. Chronopotentiograms for t
Page 632 and 633:
Figure 4. Potentiometric titrations
Page 634 and 635:
Experimental solubilization tests w
Page 636 and 637:
[13] H. Flood T. Förland and K. Mo
Page 638 and 639:
1. Introduction The separation of l
Page 640 and 641:
Figure 4. Synthesis of amides 11-15
Page 642 and 643:
1. Introduction Over the recent yea
Page 644 and 645:
2.3.2 Set-up We set up a single HFM
Page 646 and 647:
lower flow rates, Am(III) would be
Page 649 and 650:
THE POTENTIAL OF NANO- AND MICROPAR
Page 651 and 652:
efficiently and stable. This can be
Page 653 and 654:
Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
Page 657:
[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
Page 662 and 663:
Figure 3. Schematic drawing of the
Page 664 and 665:
(24), 8-PhPO(OH)-O-COSAN (25), and
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REFERENCES [1] Kyrš M., +H PiQHN S
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1. Introduction A heavy-water CANDU
Page 670 and 671:
These data show that fuel lifetime
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RECENT PROGRESSES ON PARTITIONING S
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hot tests (See Table2) was enough f
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trace amount of Am and Eu. The HBTM
Page 679 and 680:
6. Conclusion Declassification of t
Page 681:
POSTER SESSION BASIC PHYSICS: NUCLE
Page 684 and 685:
1. Introduction Among the large num
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The simulation of the spallation pr
Page 688 and 689:
Table 1. Parameters of the two coll
Page 690 and 691:
Figure 4. Radial distribution of th
Page 692 and 693:
6. The neutron escape line The comm
Page 694 and 695:
Figure 7. Neutron background at the
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RECENT CAPTURE CROSS-SECTIONS VALID
Page 699 and 700:
Figure 1. The GENEPI accelerator an
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2.3.3 Neutron flux measurements •
Page 703 and 704:
Figure 6. Time spectrum of 3 He gas
Page 705 and 706:
4. Analysis 4.1 Background subtract
Page 707 and 708:
Figure 11. ENDF/B-VI, JEF2.2 and JE
Page 709 and 710:
DOUBLE DIFFERENTIAL CROSS-SECTION F
Page 711 and 712:
3. Conclusion Double differential c
Page 713 and 714:
Figure 3. Preliminary results of do
Page 715 and 716:
MEASUREMENTS OF PARTICULE EMISSION
Page 717 and 718:
2. Experimental set-up The experime
Page 719: 4. Results Figure 3 presents neutro
Page 722 and 723: 1. Introduction Intermediate-energy
Page 724 and 725: Table 1. Relative neutron-induced c
Page 726 and 727: elow about 70 MeV [24] , where σ n
Page 728 and 729: Since for sub-actinides Γ f /Γ n
Page 730 and 731: [10] V.P. Eismont, A.V. Prokofiev,
Page 733 and 734: NUCLEON-INDUCED FISSION CROSS-SECTI
Page 735 and 736: Figure 1. Scheme of the new code Z
Page 737 and 738: Figure 3. Neutron-induced fission c
Page 739: REFERENCES [1] J. Raynal, Proceedin
Page 742 and 743: 1. Introduction During the past few
Page 744 and 745: (same surface and 0.5 mm thickness)
Page 746 and 747: Figure 2. Dependence of the total a
Page 748 and 749: Figure 3. Neutron radiative capture
Page 750 and 751: [8] MCNP, A General Monte Carlo Cod
Page 752 and 753: 1. Introduction New reactors using
Page 754 and 755: Figure 1. Excited states of 209 Bi
Page 756 and 757: Figure 3. The fission probability o
Page 759 and 760: MEASUREMENT OF DOUBLE DIFFERENTIAL
Page 761 and 762: Figure 1. Global view of the experi
Page 763 and 764: To get the proton (deuteron) energy
Page 765 and 766: 3.1 Corrections Several corrections
Page 767 and 768: Figure 11. Active target fraction (
Page 769: d 2 σ Figure 14. Proton for n + Pb
Page 773 and 774: eactions, since the pre-equilibrium
Page 775 and 776: calculate the very short-lived radi
Page 777 and 778: cross-sections; the secondary react
Page 779 and 780: All possible nuclear reactions will
Page 781 and 782: A STUDY ON BURNABLE ABSORBER FOR A
Page 783 and 784: 2. Burnable absorber for HYPER 2.1
Page 785 and 786: Table 2. One-group effective cross-
Page 787 and 788: of the core, is directly determined
Page 789 and 790: Figure 4. Required proton beam curr
Page 791 and 792: Figure 8. 10 B depletion in HYPER-H
Page 793: POSTER SESSION TRANSMUTATION SYSTEM
Page 796 and 797: 1. Introduction In the framework of
Page 798 and 799: Φ >1 MeV = 1.0 10 13 to 1.0 x 10 1
Page 800 and 801: 3. Irradiation targets and irradiat
Page 802 and 803: e transmuted in BR2 hence remain va
Page 804 and 805: Table 6. Atom percent concentration
Page 806 and 807: advantage, with respect to FRs, of
Page 809 and 810: ENHANCEMENT OF ACTINIDE INCINERATIO
Page 811 and 812: Here Σ fC , ( E) are the fission a
Page 813 and 814: pellet and the steel cladding. In o
Page 815 and 816: Table 3.Neutronics parameters of hy
Page 817 and 818: Figure 3. Neutron spectra averaged
Page 819 and 820: containing FA with B 4 C cladding i
Page 821:
REFERENCES [1] ANSALDO Technical Re
Page 824 and 825:
1. Introduction At present, there a
Page 826 and 827:
target means a change in k and the
Page 828 and 829:
Following the normal procedure for
Page 830 and 831:
Acknowledgements This study has bee
Page 832 and 833:
1. ADS description A conceptual des
Page 834 and 835:
Substitution of (9) into (8), and u
Page 836 and 837:
With the coupling LAHET + MCNP-DSP,
Page 838 and 839:
Figure 3. Comparison for 1 and 5 pu
Page 841 and 842:
MOLTEN SALTS AS POSSIBLE FUEL FLUID
Page 843 and 844:
2. The fuel salt for MSB concept Ma
Page 845 and 846:
and minor actinides must be removed
Page 847 and 848:
4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
Page 851:
REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855:
1. Introduction The Energy Amplifie
Page 856 and 857:
Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
Page 860 and 861:
Table 7. Neutron flux distributions
Page 862 and 863:
Table 8. Displacement rates DPA/yea
Page 865 and 866:
DEEP UNDERGROUND TRANSMUTOR (PASSIV
Page 867 and 868:
passive state. By operating at a hi
Page 869 and 870:
I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
Page 873 and 874:
RADIATION CHARACTERISTICS OF PWR MO
Page 875 and 876:
Table 1. Radiotoxicity of actinides
Page 877 and 878:
RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880:
Table 1. Radiotoxicity of actinides
Page 881 and 882:
INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884:
an international base to combine ef
Page 885:
• Second topic: interaction of pr
Page 888 and 889:
1. Introduction The role of acceler
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
Page 895 and 896:
During conceptual investigations of
Page 897 and 898:
delay, interface and computer. The
Page 899 and 900:
2. Channel-vessel design of ADS bla
Page 901 and 902:
Table 1. Characteristics of the ful
Page 903:
[14] Karavaev G.N., Kiselev G.V., M
Page 906 and 907:
1. Introduction The problem of nucl
Page 908 and 909:
Table 3. Radiotoxicity in americium
Page 910 and 911:
Table 5. Characteristics of station
Page 912 and 913:
1. Introduction The atomic power en
Page 914 and 915:
of lead-bismuth target are given in
Page 917 and 918:
CRITICAL AND SUB-CRITICAL GT-MHRs F
Page 919 and 920:
Table 1. Basic GT-MHR reactor param
Page 921 and 922:
Figure 2. Typical change of the ave
Page 923 and 924:
Scenario S4. This case is actually
Page 925 and 926:
Figure 3. A change in radiotoxicity
Page 927:
[13] P. Goberis, Modelling of Innov
Page 930 and 931:
1. Introduction The Nuclear Enginee
Page 932 and 933:
Some simplifications have been made
Page 934 and 935:
Figure 3. Velocity vectors Some of
Page 936 and 937:
Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
Page 940 and 941:
1. Introduction Actually, we notice
Page 942 and 943:
This problem can be solved by using
Page 944 and 945:
The evaluations obtained in [2] hav
Page 946 and 947:
REFERENCES [1] Management and Dispo
Page 948 and 949:
1. Background Radiation background
Page 950 and 951:
the long-term hazard of spent fuel,
Page 952 and 953:
In a transmutation fuel cycle inclu
Page 954 and 955:
Figure 4. Potential biological haza
Page 956 and 957:
cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
Page 961 and 962:
ORDER FORM OECD Nuclear Energy Agen
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