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higher than 99% of 239 Pu, and higher than 95% in the rest of the offending nuclei. An overall goal is to eliminate about 95% of the TRU. The final answer to the question of the capability of the pebble to withstand the high neutron fluence has to be of an experimental nature, but it is important to asses that the sought value of fuel burn-up does not result in an unbearable number of collisions per C atom. This point supports the feasibility of massive TRU elimination by an ADS pebble-bed transmutator. REFERENCES [1] NEA (OECD Nuclear Energy Agency), Waste Management Programmes in the NEA/OECD Member Countries, ISBN 92-64-26033-1, Paris, France, (1998). [2] Barret L. et al., A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology, DOE/RW-0519, (October 1999). [3] Mark J.C., Explosive Properties of Reactor-grade Plutonium in Science and Global Security, Vol. 4, No. 1, pp. 111-128 (1993). [4] Bowman C.D., Venneri F., Underground Super-criticality from Plutonium and Other Fissile Material, in Science and Global Security 5, pp. 279-303 (1996). [5] Peterson P.F., Long Term Safeguards and Security Parameters for Plutonium in Geologic Repositories, in Science and Global Security 6, pp. 1-29 (1996). [6] Bowman C.D. et al., Nuclear Energy Generation and Waste Transmutation Using an Accelerator-driven Intense Thermal Neutron Source, Nuclear Instr. and Methods A230, 336 (1992). [7] Rubbia C. et al., A Realistic Plutonium Elimination Scheme with Fast Energy Amplifiers and Thorium-plutonium Fuel, CERN/AT/95-33(et) (1995). [8] Arnold H et al., Experimental Verification of Neutron Phenomenology in Lead and Transmutation by Adiabatic Resonance Crossing in Accelerator Driven Systems, Physics Letters B 458, 167-180 (1999). [9] Salvatores M., Slesarev I., Tchistiakov A. and Ritter G., The Potential of Accelerator Driven Systems for Transmutation or Power Production USING Thorium or Uranium Fuel Cycles, Nuc. Sci. Eng, 126, 333 (1997). [10] Salvatores M. et al., Nucl. Inst. and Methods A414, (1998) 5-20. [11] Venneri F. et al., Accelerator Driven Transmutation of Waste (ATW) Technical Review at MIT, LANL Report, LA-UR-98-608 (1998). 554
[12] Salvatores M., Spiro M., The INCA Project: Radwaste Incineration Using Accelerators, Nuclear Europe Worldscan, 7-8 (1997) 116. [13] Schulten R. et al., The Pebble-bed High Temperature Reactor as a Source of Nuclear Process Heat, JUL-1113-RG, KFA-Julich (1974). [14] The High Temperature Reactor and Nuclear Process Heat Applications (Special issue), Nuclear Engineering and Design, 78, 1984. [15] Kugeler K., Schulten, R., Hochtemperaturreaktortechnik, Springer Verlag, 1989. [16] Kugeler K., Philippen P.W., The Potential of Self-acting Safety Features of High Temperature Reactors, Kerntechnik 61, 1996, 5-6. [17] Schenk W. et al., Fission Products Release from Spherical Fuel Elements under Accidents Temperatures Conditions, KFA, Julich, Jul-2091, Oct. 1986. [18] Saphier D., DSNP Models Used in the Pebble-bed HTGR Dynamic Simulation, Final Rep., Vol. 2, RRASG-108-84, Apr. (1984). [19] Schmidt P., Lohnert G., The Modular HTR Power Plant – Description of the Plant and Safety Concept, Interatom GmbH, 5060 Bergisch Gladbach, June (1986). [20] Briesmeister J.F., MCNP – A General Monte Carlo N-Particle Transport Code, LA-2625-M, Los Alamos National Laboratory (1993). [21] Drake M.K. (Ed), Data Formats and Procedures for the ENDF Neutron Cross-section Library, BNL-0274 (T-601, ID-4500), ENDF-102 Vol. 1, Brookhaven National Laboratory (1970) (Rev. 1974). [22] Nordborg C., Salvatores M., Status of the JEFF Evaluated Data Library, Proceedings of the International Conference on Nuclear Data for Science and Technology, Gatlinburg, P. 680 (1994). [23] Rubbia C., Resonance Enhanced Nuclear Waste Transmutation, Report University of Pisa (May 11 th , 1999). [24] Rubbia C., University of Pavia Report, 1999. [25] Perez R.B. et al., Dynamic Review of a Proposed Helium Cooled Reactor Design for Minor Actinide Burning, Technical Report JUSAP-39, Oak Ridge National Laboratory, 1999. 555
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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:
Page 502 and 503:
Regarding switching off the beam, o
Page 504 and 505: Figure 3. Beam blocking 10 min (200
Page 506 and 507: Figure 7. A possible scenario for n
Page 508 and 509: [15] Greenspan E. et al., The Encap
Page 510 and 511: 1. Introduction In the EADF design
Page 512 and 513: Equation (6) can be improved by con
Page 514 and 515: where L is obtained by a summation
Page 516 and 517: Figure 1. The natural convection im
Page 518 and 519: Figure 4 shows the temperature tren
Page 520 and 521: [12] P.H. Wakker, Thermal Hydraulic
Page 522 and 523: 1. Introduction Research and develo
Page 524 and 525: Table 2. Core design parameters for
Page 526 and 527: 2.2 Representation of MA transmutat
Page 528 and 529: Figure 1(b) shows the cases for the
Page 530 and 531: It is found that the higher MA tran
Page 532 and 533: REFERENCES [1] T. Ikegami, H. Hayas
Page 534 and 535: 1. Introduction The management of t
Page 536 and 537: 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.,
Page 544 and 545: 1. Introduction and background The
Page 546 and 547: neutron source, the reactor can mai
Page 548 and 549: atoms. For fuel region Rf = 2.5 cm,
Page 550 and 551: Figure 3. Neutron flux spectra for
Page 552 and 553: A possible way to maintain the k ef
Page 557 and 558: TRANSMUTATION OF NUCLEAR WASTES WIT
Page 559 and 560: Figure 1. PBT conceptual view Table
Page 561 and 562: very tight holders for fission frag
Page 563 and 564: 5. Cooling system A preliminary des
Page 565 and 566: spectral densities [10,11] and can
Page 567 and 568: MYRRHA, A MULTI-PURPOSE ADS FOR R&D
Page 569 and 570: hexagonal assemblies of 122 mm plat
Page 571 and 572: to achieve the requested performanc
Page 573 and 574: 3 MYRRHA associated R&D programme F
Page 575 and 576: collaboration with Forschungszentru
Page 577: • Industrial partners, in particu
Page 580 and 581: 1. Introduction The transmutation o
Page 582 and 583: Existing accelerators have been des
Page 584 and 585: suggested to look for an innovative
Page 586 and 587: Table 1. Main lead-bismuth eutectic
Page 588 and 589: 4.3 The core The basic fuel sub-ass
Page 590 and 591: 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
Page 599 and 600: atio. Given this rate of destructio
Page 601 and 602: Figure 5. Irradiated TRISO particle
Page 603 and 604: in ceramic-coated microspheres of t
Page 605 and 606:
(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
Page 655 and 656:
Scheme 7. Magnetic silica particles
Page 657:
[13] L.H. Delmau, N. Simon, M.J. Sc
Page 660 and 661:
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
Page 666 and 667:
REFERENCES [1] Kyrš M., +H PiQHN S
Page 668 and 669:
1. Introduction A heavy-water CANDU
Page 670 and 671:
These data show that fuel lifetime
Page 673 and 674:
RECENT PROGRESSES ON PARTITIONING S
Page 675 and 676:
hot tests (See Table2) was enough f
Page 677 and 678:
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
Page 686 and 687:
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
Page 697 and 698:
RECENT CAPTURE CROSS-SECTIONS VALID
Page 699 and 700:
Figure 1. The GENEPI accelerator an
Page 701 and 702:
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 and 770:
d 2 σ Figure 14. Proton for n + Pb
Page 771 and 772:
HIGH AND INTERMEDIATE ENERGY NUCLEA
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
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1. Introduction In the framework of
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Φ >1 MeV = 1.0 10 13 to 1.0 x 10 1
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3. Irradiation targets and irradiat
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e transmuted in BR2 hence remain va
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Table 6. Atom percent concentration
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advantage, with respect to FRs, of
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ENHANCEMENT OF ACTINIDE INCINERATIO
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Here Σ fC , ( E) are the fission a
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pellet and the steel cladding. In o
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Table 3.Neutronics parameters of hy
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Figure 3. Neutron spectra averaged
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containing FA with B 4 C cladding i
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REFERENCES [1] ANSALDO Technical Re
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1. Introduction At present, there a
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target means a change in k and the
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Following the normal procedure for
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Acknowledgements This study has bee
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1. ADS description A conceptual des
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Substitution of (9) into (8), and u
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With the coupling LAHET + MCNP-DSP,
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Figure 3. Comparison for 1 and 5 pu
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MOLTEN SALTS AS POSSIBLE FUEL FLUID
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2. The fuel salt for MSB concept Ma
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and minor actinides must be removed
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4. Container material studies 4.1 F
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management. The major developments
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REFERENCES [1] H.J. MacPherson, Dev
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1. Introduction The Energy Amplifie
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Table 1. Main parameters of the EAD
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Table 5. Neutron balance in the who
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Table 7. Neutron flux distributions
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Table 8. Displacement rates DPA/yea
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DEEP UNDERGROUND TRANSMUTOR (PASSIV
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passive state. By operating at a hi
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I have proposed using an accelerato
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Figure 1. Layout of deep undergroun
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RADIATION CHARACTERISTICS OF PWR MO
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Table 1. Radiotoxicity of actinides
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RADIATION CHARACTERISTICS OF URANIU
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Table 1. Radiotoxicity of actinides
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INTERNATIONAL CO-OPERATION ON CREAT
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an international base to combine ef
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• Second topic: interaction of pr
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1. Introduction The role of acceler
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MEPI within the framework of Projec
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NEW ORIGINAL IDEAS ON ACCELERATOR D
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During conceptual investigations of
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delay, interface and computer. The
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2. Channel-vessel design of ADS bla
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Table 1. Characteristics of the ful
Page 903:
[14] Karavaev G.N., Kiselev G.V., M
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1. Introduction The problem of nucl
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Table 3. Radiotoxicity in americium
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Table 5. Characteristics of station
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1. Introduction The atomic power en
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of lead-bismuth target are given in
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CRITICAL AND SUB-CRITICAL GT-MHRs F
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Table 1. Basic GT-MHR reactor param
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Figure 2. Typical change of the ave
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Scenario S4. This case is actually
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Figure 3. A change in radiotoxicity
Page 927:
[13] P. Goberis, Modelling of Innov
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1. Introduction The Nuclear Enginee
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Some simplifications have been made
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Figure 3. Velocity vectors Some of
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Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
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1. Introduction Actually, we notice
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This problem can be solved by using
Page 944 and 945:
The evaluations obtained in [2] hav
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REFERENCES [1] Management and Dispo
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1. Background Radiation background
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the long-term hazard of spent fuel,
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In a transmutation fuel cycle inclu
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Figure 4. Potential biological haza
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cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
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ORDER FORM OECD Nuclear Energy Agen
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