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1. Introduction The term ADS comprehensively includes all non-self sustaining fissioning neutron multiplying assemblies which are driven by an external neutron source provided by a charged particle accelerator and a neutron producing target. ADS systems under current study worldwide include both thermal and fast neutron multiplying media comprised of either liquid or solid (lattice) fuel and driven by either cyclotron or linear proton accelerators and spallation targets (liquid and solid) of various heavy metals. The underlying missions targeted for ADS systems span the range from nuclear waste incineration with ancillary power production through power production with integral waste self-incineration to finally, excess neutron production for the purpose of isotope production via neutron capture reactions on targets. The OECD/NEA expert group on “Comparative Study of ADS and FR’s in Advanced Fuel Cycles” [1] confined its scope of inquiry to a subset of ADS configurations – those targeted for nuclear waste incineration with ancillary power production, and specifically those which operate on a fast neutron spectrum with a solid fuel pin lattice. Moreover, the expert group set a requirement of maximum “support ratio” (i.e. maximum energy from the reactors in the complex compared to energy from the ADS in the complex) which leads to inert matrix fuel (i.e. 238 U and 232 Th – free fuel) for the ADS. The scope of this discussion of safety strategy is similarly confined in scope. Even within the limited scope, a range of possibilities exists. The ADS might be a minor actinide (MA) burner or a TRU burner; the physics and safety characteristics of these cases differ because of differences in their values of βeff (which helps to set the degree of sub-criticality of the ADS) and in their reactivity burn-up swing (which helps to set the control strategy). The choice of coolant (liquid metal or gas) and fuel type (oxide, nitride, metal) also distinguishes members of the ADS class considered by the expert group. The choice of recycle (partitioning) technology (aqueous, dry) directly affects the architecture of the energy complex and indirectly affects the ADS itself. Figure 1 illustrates the several energy producing complexes which were considered by the expert group and identifies the waste management function of the ADS studied in the single strata architecture (3B) and (the double strata architecture (4)). The fast spectrum, solid fuel, waste incinerating class of ADS considered by the expert group shares with all ADS a distinction from critical reactors in relying on an external neutron source rather than a self generated delayed neutron source for maintaining the neutron population in balance – with attendant changes in dynamic response and in control strategy. However, the class of ADS considered here offers design and safety challenges which are unique vis-à-vis other ADS classes in the areas of burn-up control compensation and reactivity feedback characteristics; these unique challenges are traceable to a small number of salient design features which derive directly from the requirements of the TRU or MA incineration mission – with ancillary power production. The salient design features of the ADS whose safety features were considered by the OECD/NEA expert group include the following: • Fertile-free transuranic or minor actinide fuel. • Multiple recycle of fuel to (near) complete fission incineration of transuranics. • Fast neutron spectrum. • Choice of coolant (Na, Pb-Bi or He). • Sub-delayed critical operating state. • External neutron source created via spallation reactions of high-energy protons on a heavy atom spallation target. 96
The approach taken by the expert group to identify ADS safety issues and discuss strategies for addressing them was as follows. First, the top level safety functions to be satisfied for any fission chain reacting system (reactor or ADS) were enumerated. Then, the distinguishing features of the class of ADS considered here were traced back to the mission assigned to it in the complex; as a way to indicate which features (and safety issues) would be changed by a change in mission requirements. Then, an impact matrix was constructed (with “safety function” columns and “distinguishing feature” rows) to identify where the ADS distinguishing features have raised safety-relevant challenges which are different from the more familiar situation for a fast reactor. Finally, for each identified challenge, a set of alternative safety strategies for addressing it were discussed with the views that: Figure 1. Nuclear fuel cycle schemes 2QFHÃ7KURXJKÃ 3XÃ%XUQLQJÃ Pu Pu LWR LWR LWR FR Pu MA+Losses 758Ã%XUQLQJÃLQÃ)5Ã$ 'RXEOHÃ6WUDWDÃ U An LWR TRU Pu Pu FR LWR LWR FR Pu Losses MA Losses An FR/ADS Losses HLW 758Ã%XUQLQJÃLQÃ$'6Ã% )5Ã6WUDWHJ\Ã LWR TRU ADS An U nat FR An Losses Losses 97
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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
Page 46 and 47: separating troublesome fission prod
Page 48 and 49: REFERENCES [1] L.H. Baetslé, Ch. D
Page 51 and 52: SESSION III Partitioning Chairs: J.
Page 53 and 54: OVERVIEW OF THE HYDROMETALLURGICAL
Page 55 and 56: 2.1.3 Consequences Owing to the fac
Page 57 and 58: The extraction and separation mecha
Page 59 and 60: extractant was observed. As a conse
Page 61 and 62: 2.3.2 Examples of strategies and
Page 63 and 64: 3. Conclusions and perspectives 3.1
Page 65 and 66: SESSION IV Basic Physics, Materials
Page 67 and 68: TRANSMUTATION: A DECADE OF REVIVAL
Page 69 and 70: 2.1 The IFR concept and the homogen
Page 71 and 72: 2.3 Dedicated systems Making again
Page 73 and 74: compound “macro-dispersed” in M
Page 75 and 76: Figure 3. Sketch of ADS, liquid met
Page 77 and 78: 3.3.2.1 The MEGAPIE project [40] ME
Page 79 and 80: 3.3.2.2 The MUSE experiments The MU
Page 81 and 82: Figure 8. Comparison of the neutron
Page 83 and 84: 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 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 136 and 137: 3.2.5.2 JNC JNC is considering the
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
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
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SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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Figure 1. The natural convection im
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Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
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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
Page 813 and 814:
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
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
Page 834 and 835:
Substitution of (9) into (8), and u
Page 836 and 837:
With the coupling LAHET + MCNP-DSP,
Page 838 and 839:
Figure 3. Comparison for 1 and 5 pu
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MOLTEN SALTS AS POSSIBLE FUEL FLUID
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2. The fuel salt for MSB concept Ma
Page 845 and 846:
and minor actinides must be removed
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4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
Page 851:
REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855:
1. Introduction The Energy Amplifie
Page 856 and 857:
Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
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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
Page 877 and 878:
RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880:
Table 1. Radiotoxicity of actinides
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INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884:
an international base to combine ef
Page 885:
• Second topic: interaction of pr
Page 888 and 889:
1. Introduction The role of acceler
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
Page 895 and 896:
During conceptual investigations of
Page 897 and 898:
delay, interface and computer. The
Page 899 and 900:
2. Channel-vessel design of ADS bla
Page 901 and 902:
Table 1. Characteristics of the ful
Page 903:
[14] Karavaev G.N., Kiselev G.V., M
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1. Introduction The problem of nucl
Page 908 and 909:
Table 3. Radiotoxicity in americium
Page 910 and 911:
Table 5. Characteristics of station
Page 912 and 913:
1. Introduction The atomic power en
Page 914 and 915:
of lead-bismuth target are given in
Page 917 and 918:
CRITICAL AND SUB-CRITICAL GT-MHRs F
Page 919 and 920:
Table 1. Basic GT-MHR reactor param
Page 921 and 922:
Figure 2. Typical change of the ave
Page 923 and 924:
Scenario S4. This case is actually
Page 925 and 926:
Figure 3. A change in radiotoxicity
Page 927:
[13] P. Goberis, Modelling of Innov
Page 930 and 931:
1. Introduction The Nuclear Enginee
Page 932 and 933:
Some simplifications have been made
Page 934 and 935:
Figure 3. Velocity vectors Some of
Page 936 and 937:
Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
Page 940 and 941:
1. Introduction Actually, we notice
Page 942 and 943:
This problem can be solved by using
Page 944 and 945:
The evaluations obtained in [2] hav
Page 946 and 947:
REFERENCES [1] Management and Dispo
Page 948 and 949:
1. Background Radiation background
Page 950 and 951:
the long-term hazard of spent fuel,
Page 952 and 953:
In a transmutation fuel cycle inclu
Page 954 and 955:
Figure 4. Potential biological haza
Page 956 and 957:
cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
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ORDER FORM OECD Nuclear Energy Agen
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