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3.2.5.2 JNC JNC is considering the same method as for the partitioning process. 3.2.5.3 CRIEPI CRIEPI is developing molten-salt electrorefining and reductive extraction, which is similar to the partitioning process. Electrorefining forms the main part of the pyro-reprocessing method. Feasibility was confirmed through an in-house study and international joint research, and the process is now at the stage of engineering experiments. Feasibility of the conversion of oxides of spent fuel to metal, and of the spent-salt treatment process, are still to be confirmed. 3.2.6 Conclusion R&D at the three research institutes has resulted in establishment of processes for P&T technology with the expected performance. The aims of Phase I R&D have thus been achieved. R&D in Phase II has experienced some delays, the primary reasons being that Japan is redefining its entire FBR programme, and facilities to handle MAs and other materials have yet to be constructed. In carrying out further R&D, it is important to promote cooperation with domestic and foreign organizations in order that experimental facilities – including those for engineering experiments – can be used efficiently. 3.3 Technical issues The implementation of experiments to demonstrate processes using actual HLLW is an issue common to the three organizations. Also common to JAERI and JNC, which are developing aqueous partitioning processes, are development of a method to more efficiently separate MAs and rare-earth elements, and technologies to reduce the volume of secondary waste. At CRIEPI, where dry partitioning is being developed, the main technical issues in the handling of molten chlorides are material development and molten-salt transport technology. Common issues to the three organisations are preparation of a database on fuel irradiation behavior for performance analysis, and development of fuel fabrication technology. 4. Effects and significance of partitioning and transmutation technology 4.1 Radioactive inventory in waste It is a social imperative to minimise, as far as possible, the generation of hazardous waste produced by industrial activities. Reduction of long-term radioactive inventory through the removal of long-lived nuclides from HLW by P&T technology helps to meet this requirement. If, for example, 99% of MAs contained in spent fuel can be removed, the toxicity of the spent fuel after several hundred years following reprocessing will be equal to the toxicity of the same amount of natural uranium as used in the production of the original fuel. 136
4.2 Effects on geological disposal 4.2.1 Long-term safety • Effects on the underground water migration scenario: Maximum dose can be reduced by about two orders of magnitude by separating and removing 99% of the 135 Cs, and 99% or more of the Np and Am, which are parent nuclides of 229 Th. • Effects on the human intrusion scenario: Risks can be reduced by two orders of magnitude by separating and removing 99-99.99% of the actinide elements. 4.2.2 Impact on geological disposal site design Approximately two-thirds of the heat from HLW is generated by Cs and Sr, and separation and removal of these elements would shorten the required storage period and reduce the size of the site. The HLW storage period could be reduced by separating and removing exothermic nuclides. In addition, disposal site design could be rationalized by, for example, disposing of the HLW in one large cavity rather than in several smaller ones. 4.3 Effective use of resources Among the materials in HLW, some can be used effectively as resources. For example platinum group elements are widely used as catalysts to reduce nitrogen oxides in vehicle exhaust gases, and so on. However, prior to actual application, clearance level issues are to be solved. 4.4 Reduction of MA and LLFP inventory, and the times required Even if P&T technology is employed, some MAs and LLFPs will remain in the waste, and final disposal of such waste will eventually be necessary. An oxide-fuelled or metallic-fuelled fast reactor can transmute MAs from more than five or six LWRs every year. While an ADS with one quarter of thermal output of a LWR can transmute MAs from more than ten LWRs (about 250 kg per year). 4.5 Generation of secondary waste The aqueous partitioning process, like PUREX reprocessing, generates secondary waste. Compared with reprocessing, however, the volume of secondary waste is lower because P&T technology deals with the very limited quantities of HLLW generated by reprocessing. In the dry-type partitioning process, molten salts and liquid metals are used as solvents, and metallic Li is used as a reducer. These solvents and reducers are less susceptible to degradation by radiation, and may be recycled in the system. But there is almost no experience of using this process on an industrial scale. To evaluate the secondary waste volume, further investigations and experience using actual materials are needed. 137
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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
Page 85 and 86: goals in this field. Since once-thr
Page 87 and 88: • The use of Thorium in PWRs alwa
Page 89 and 90: • Understanding of the role of AD
Page 91 and 92: [17] Y. Arai, T. Ogawa, Research on
Page 93: SESSION V Transmutation Systems and
Page 96 and 97: 1. Introduction The term ADS compre
Page 98 and 99: • Safety should be “designed in
Page 100 and 101: 3. Minor actinide and/or transurani
Page 102 and 103: Table 2. Values of Dj (neutron cons
Page 104 and 105: Table 4. Delayed neutron fraction I
Page 106 and 107: Figure 4. η (Neutrons released per
Page 108 and 109: Table 5. ADS Distinguishing feature
Page 110 and 111: While a favourable ADS safety featu
Page 112 and 113: Optimised mixes of MA and Pu can be
Page 114 and 115: Moreover, the fuel is where neutron
Page 116 and 117: REFERENCES [1] L. Van den Durpel et
Page 118 and 119: [19] D.C. Wade and E. Fujita, Trend
Page 121 and 122: POSTER SESSION Basic Physics: Nucle
Page 123: To conclude, this poster session in
Page 126 and 127: Five other papers related to ADS co
Page 129: SESSION I OVERVIEW OF NATIONAL AND
Page 132 and 133: 1. Current activities for radioacti
Page 134 and 135: 3.2 Results to date and analyses of
Page 138 and 139: 4.6 Short-term increase in radiatio
Page 140 and 141: Annex 1 R&D scheme for partitioning
Page 142 and 143: Annex 3 Members of the Advisory Com
Page 144 and 145: plutonium can be recycled in pressu
Page 146 and 147: choices and the implementation of m
Page 148 and 149: 1. Introduction Since the 5th Infor
Page 150 and 151: strata” approach which would invo
Page 153 and 154: IAEA ACTIVITIES IN THE AREA OF EMER
Page 155 and 156: actually started to do so) because
Page 157 and 158: establishment of an international R
Page 159 and 160: The accelerator driven transmutatio
Page 161 and 162: substantiate this recommendation, s
Page 163 and 164: current, advanced and innovative nu
Page 165 and 166: ACCELERATOR DRIVEN SUB-CRITICAL SYS
Page 167 and 168: demonstration of feasibility of a E
Page 169 and 170: An extended “skeleton” for ADS
Page 171 and 172: • Fertile support (uranium) is no
Page 173: 7. Conclusions The TWG under the ch
Page 176 and 177: 1. Introduction The priorities for
Page 178 and 179: In the EURATOM Fourth Framework Pro
Page 180 and 181: Table 2. Cluster on transmutation-t
Page 182 and 183: 6. Community research for the perio
Page 184 and 185: 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
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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
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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
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1. Introduction Intermediate-energy
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Table 1. Relative neutron-induced c
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elow about 70 MeV [24] , where σ n
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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
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Figure 1. Scheme of the new code Z
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Figure 3. Neutron-induced fission c
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REFERENCES [1] J. Raynal, Proceedin
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1. Introduction During the past few
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(same surface and 0.5 mm thickness)
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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
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1. Introduction New reactors using
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Figure 1. Excited states of 209 Bi
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Figure 3. The fission probability o
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MEASUREMENT OF DOUBLE DIFFERENTIAL
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Figure 1. Global view of the experi
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To get the proton (deuteron) energy
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3.1 Corrections Several corrections
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Figure 11. Active target fraction (
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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
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All possible nuclear reactions will
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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
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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
Page 836 and 837:
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
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
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
Page 910 and 911:
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
Page 917 and 918:
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
Page 934 and 935:
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
Page 946 and 947:
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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