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REFERENCES [1] R.J.M. Konings and J.L. Kloosterman, A View of Strategies for Transmutation of Actinides. Progr. Nucl. Energy, in press (IMF’6 Special Issue). [2] A. Fernandez, K. Richter, J. Somers. Preparation of Spinel (MgAl 2 O 4 ) Spheres by a Hybrid Solgel Technique. 9th Cimtec- World Ceramics Congress. Advanced in Science and Technology 15. Ceramics: Getting into the 2000’s. Part C (1999). [3] K. Richter, A. Fernandez, J. Somers, Infiltration of Highly Radioactive Materials: A Novel Approach to the Fabrication of Transmutation and Incineration Targets. J. Nucl. Mater., 1997, 249, 121. [4] N. Chauvin and J.-F. Babelot, Rapport de synthèse commun CEA/ITU sur l’expérience SUPERFACT 1, CEA Cadarache, Note Technique SDC/LEMC 96-2028 (1996). [5] J. Somers, J.P. Glatz, D. Haas, D.H. Wegen, S. Fourcaudot, C. Fuchs, A. Stalios, D. Plancq, G. Mühling, Status of the TRABANT Irradiation Experiments, in Proceedings of the International Conference on Future Nuclear Systems, Global’99, Jackson Hole, Wyoming, 1999. [6] JCPDS, International Centre for Diffraction Data, 30-1468, (1996). [7] N. Boucharat, A. Fernández, J. Somers, R.J.M. Konings, D. Haas, Fabrication of Zirconiabased Targets for Transmutation, Progr. Nucl. Energy, in press (IMF’6 Special Issue). [8] R.J.M. Konings, R. Conrad, G. Dassel, B. Pijlgroms, J. Somers, E. Toscano, J. Nucl. Mat., in press (also published as EUR Report 19138 EN (2000)). [9] N. Chauvin, R.J.M. Konings, H.J. Matzke, Optimization of Inert Matrix Fuel Concepts for Americium Transmutation. J. Nucl. Mat., 1999, 274, 105-111. 434
AMERICIUM TARGETS IN FAST REACTORS S. Pilate 1 , A.F. Renard 1 , H. Mouney 2 , G. Vambenèpe 2 1 Belgonucléaire, Brussels 2 Électricité de France, Paris & Lyon Abstract It would be advantageous to irradiate americium targets up to very large burn-ups, so as to throw them away to waste without any further reprocessing. Former studies considered the recycling of americium in conventional LWRs. But even after long irradiation times the incineration rate of americium, of the order of 50%, was not sufficient to avoid reprocessing and re-fabrication of targets. In fast reactors, americium targets could be placed in special assemblies filled with a neutron moderator material which enhances Am incineration. Recent calculations show that a burn-up of 90% in the targets could be reached upon affordable irradiation times. A major problem remains the choice of the inert support material of the targets. So far, the support materials currently envisaged have exhibited too large swelling rates. A type of support material virtually non swelling would be in the form of coated particles, like those irradiated without damage up to very high burn-ups in high temperature reactors. Studies are being launched on the feasibility of such Am targets with coated particles in fast reactors. 435
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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
Page 384 and 385: Figure 2. Microscopic capture cross
Page 386 and 387: Figure 4. k eff variation in the st
Page 388 and 389: 2.4 Neutron flux distribution One r
Page 390 and 391: etween the highest and the lowest v
Page 392 and 393: The isotope specific β eff values
Page 395: SESSION IV BASIC PHYSICS, MATERIALS
Page 398 and 399: 1. Introduction Due to its excellen
Page 400 and 401: Figure 2. Tests scheme 0 340 h. 1 0
Page 402 and 403: Figure 4. Auger depth profile conce
Page 404 and 405: Figure 8. Auger depth profile conce
Page 406 and 407: deposited at the cold zone, and the
Page 408 and 409: inner layer grows inward from the o
Page 410 and 411: [8] V.M. Fedirko, O.I. Eliseeva, V.
Page 412 and 413: 1. Introduction One of the main par
Page 414 and 415: 3. Tantalum target irradiation The
Page 416 and 417: At 10-MeV neutron irradiation, radi
Page 418 and 419: 1. Introduction HYPER (HYbrid Power
Page 420 and 421: this study, we used an orthogonal c
Page 422 and 423: Figure 5. Temperature distribution
Page 424 and 425: Figure 7. Thermal stress distributi
Page 427 and 428: FUEL/TARGET CONCEPTS FOR TRANSMUTAT
Page 429 and 430: (U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
Page 431 and 432: Figure 3. Left: Ceramograph of a (Z
Page 433: Figure 6. Left: ceramograph of a(Zr
Page 437 and 438: The reference case for all comparis
Page 439 and 440: It should be underlined that this c
Page 441 and 442: Cases Table 3. Heterogeneous recycl
Page 443 and 444: • A later step could be to add Cm
Page 445 and 446: RESEARCH ON NITRIDE FUEL AND PYROCH
Page 447 and 448: temperature for (Cm,Pu)N followed t
Page 449 and 450: Figure 1. Temperature dependence of
Page 451 and 452: The difference of two fuel pins exi
Page 453 and 454: In addition to the voltammetric stu
Page 455 and 456: 2 wt% of Pu at 773 K. For the momen
Page 457: [13] M. Akabori, M. Takano, A. Itoh
Page 460 and 461: 1. Introduction For the management
Page 462 and 463: The scientific feasibility of pluto
Page 464 and 465: Another option using a basis of sta
Page 466 and 467: 6.2.1 Inert matrices 6.2.1.1 MgAl 2
Page 468 and 469: eached respectively 38.5% and 70% F
Page 470 and 471: Figure 4. Experiments for MA transm
Page 472 and 473: Figure 5a. Ecrix B rig Figure 5b. E
Page 474 and 475: A CEA/Minatom work programme is und
Page 476 and 477: 9.3 Programme for dedicated fuels F
Page 478 and 479: [14] R.J.M. Konings et al., The EFT
Page 480 and 481: 1. Introduction An accelerator driv
Page 482 and 483: 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
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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
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Figure 3. Nuclear electricity capac
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Table 3. Experimental items at PEF
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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
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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
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Existing accelerators have been des
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suggested to look for an innovative
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Table 1. Main lead-bismuth eutectic
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4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
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HELIUM-COOLED REACTOR TECHNOLOGIES
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of its potential use in nuclear wea
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Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
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in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
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POSTER SESSION PARTITIONING M.J. Hu
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1. Introduction The study of the be
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Plutonium was simulated with the no
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The influence of uranium and pluton
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The influence of uranium and pluton
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REFERENCES [1] I.I. Nazarenko, A.M.
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1. Introduction The long-term radio
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Ce Ce 3+ Cl - Cl 2 The voltammogram
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Figure 3. Chronopotentiograms for t
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Figure 4. Potentiometric titrations
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Experimental solubilization tests w
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[13] H. Flood T. Förland and K. Mo
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1. Introduction The separation of l
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Figure 4. Synthesis of amides 11-15
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1. Introduction Over the recent yea
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2.3.2 Set-up We set up a single HFM
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lower flow rates, Am(III) would be
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THE POTENTIAL OF NANO- AND MICROPAR
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efficiently and stable. This can be
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Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
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[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
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Figure 3. Schematic drawing of the
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(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
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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
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6. Conclusion Declassification of t
Page 681:
POSTER SESSION BASIC PHYSICS: NUCLE
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1. Introduction Among the large num
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The simulation of the spallation pr
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Table 1. Parameters of the two coll
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Figure 4. Radial distribution of th
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6. The neutron escape line The comm
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Figure 7. Neutron background at the
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RECENT CAPTURE CROSS-SECTIONS VALID
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Figure 1. The GENEPI accelerator an
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2.3.3 Neutron flux measurements •
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Figure 6. Time spectrum of 3 He gas
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4. Analysis 4.1 Background subtract
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Figure 11. ENDF/B-VI, JEF2.2 and JE
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DOUBLE DIFFERENTIAL CROSS-SECTION F
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3. Conclusion Double differential c
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Figure 3. Preliminary results of do
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MEASUREMENTS OF PARTICULE EMISSION
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2. Experimental set-up The experime
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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
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[10] V.P. Eismont, A.V. Prokofiev,
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NUCLEON-INDUCED FISSION CROSS-SECTI
Page 735 and 736:
Figure 1. Scheme of the new code Z
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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
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Figure 3. Neutron radiative capture
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[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
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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
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HIGH AND INTERMEDIATE ENERGY NUCLEA
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eactions, since the pre-equilibrium
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calculate the very short-lived radi
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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
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2. Burnable absorber for HYPER 2.1
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Table 2. One-group effective cross-
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of the core, is directly determined
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Figure 4. Required proton beam curr
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Figure 8. 10 B depletion in HYPER-H
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POSTER SESSION TRANSMUTATION SYSTEM
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1. Introduction In the framework of
Page 798 and 799:
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
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
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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
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[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
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[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
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• 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
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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
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REFERENCES [1] White Book of Nuclea
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ORDER FORM OECD Nuclear Energy Agen
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