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2.2.2 Targets for heterogeneous recycling................................................................. 145 2.2.2.1 Fabrication of AmO 2 target pins ....................................................... 145 2.2.2.2 Effect of curium on target fabrication ............................................... 146 2.2.2.3 Fabrication of targets for transmutation of fission products............... 146 2.3 Transmutation of minor actinides ................................................................................ 147 2.3.1 Physics and methods of transmutation ............................................................. 147 2.3.1.1 Physics ............................................................................................ 147 2.3.1.2 Methods........................................................................................... 149 2.3.2 Transmutation of minor actinides in thermal reactors ....................................... 150 2.3.2.1 Present day PWR reactor ................................................................. 150 2.3.2.2 Molten salt reactor ........................................................................... 154 2.3.3 Transmutation of minor actinides in fast reactors............................................. 154 2.3.3.1 MOX-fuelled fast reactor ................................................................. 154 2.3.3.2 Minor actinides transmutation in metal-fuelled fast reactor................ 160 2.3.4 Transmutation of minor actinides and fission products in dedicated systems ..... 162 2.3.4.1 Dedicated minor actinide burner reactor............................................ 163 2.3.4.2 Accelerator-driven transmutation systems ......................................... 164 2.3.5 <strong>Nuclear</strong> data of minor actinides and long-lived fission products........................ 171 2.3.6 Interaction between plutonium incineration and minor actinide production........ 173 2.3.6.1 Present day PWRs............................................................................ 173 2.3.6.2 Other alternatives............................................................................. 173 2.3.6.3 FRs without blanket (FBuR)............................................................. 174 2.4 Transmutation of long-lived fission products ............................................................... 175 2.4.1 Transmutation of fission products in fission reactors........................................ 175 2.4.1.1 Transmutation of 99 Tc and 129 I .......................................................... 175 2.4.1.2 Transmutation in fast reactors .......................................................... 176 2.4.1.3 Transmutation in light water reactors................................................ 177 2.4.1.4 Transmutation in heavy water reactors.............................................. 177 2.4.1.5 Transmutation in thermal high flux reactors...................................... 177 2.4.1.6 Conclusions ..................................................................................... 178 2.4.2 <strong>Nuclear</strong> data on fission products...................................................................... 178 3. DESCRIPTION OF CURRENT TRENDS IN P&T RESEARCH......................................................... 179 3.1 Current R&D activities............................................................................................... 179 3.1.1 OMEGA programme....................................................................................... 179 3.1.2 SPIN programme ............................................................................................ 180 3.2 Summary of current strategy studies............................................................................ 182 3.2.1 European Union strategy study........................................................................ 182 3.2.1.1 Reference and P&T scenario ............................................................ 182 3.2.1.2 Potential radiotoxicity ...................................................................... 183 3.2.2 Studies in Japan .............................................................................................. 183 3.2.2.1 MOX-fuelled FBR ........................................................................... 184 3.2.2.2 Actinide burner reactor..................................................................... 185 6
4. IMPACT OF P&T ON RISK ASSESSMENT AND WASTE MANAGEMENT....................................... 187 4.1 Introduction and definition of radiotoxicity and risk..................................................... 187 4.1.1 Risks in the back-end of the fuel cycle ............................................................. 187 4.1.2 Exposure related risk....................................................................................... 188 4.1.3 Radiotoxic inventory of radionuclides and irradiated fuel ................................. 189 4.1.4 Assessment of the radiological risk .................................................................. 190 4.1.5 Decision framework ........................................................................................ 190 4.1.6 Conclusion and recommendations.................................................................... 191 4.2 Radiotoxic inventory of waste ..................................................................................... 191 4.3 Possible impact of P&T on TRU reduction.................................................................. 195 4.3.1 Necessary facilities to implement P&T ............................................................ 195 4.3.1.1 Inventories of minor actinides to be processed in a AFC scenario ...... 195 4.3.1.2 Recycling scenarios for power reactors ............................................. 197 4.3.1.3 Results............................................................................................. 200 4.3.1.4 Influence of non-recycling of curium................................................. 201 4.3.1.5 Separation performance objective ..................................................... 202 4.3.1.6 Conclusions ..................................................................................... 203 4.3.2 Impact of separated nuclides ........................................................................... 205 4.4 Risk and hazard assessment over time ......................................................................... 206 4.4.1 Pre-disposal waste management of RFC operations ......................................... 206 4.4.2 Radiological impact of waste discharges.......................................................... 208 4.4.3 Impact of P&T operations on waste management of AFC ................................ 210 4.4.4 Global fuel cycle situation for waste management decisions ............................. 211 4.4.5 Evolution of long-term radiotoxic inventory..................................................... 214 4.4.6 Role and impact of cut-off period .................................................................... 215 4.5 Waste management concepts....................................................................................... 217 4.5.1 OTC concepts for direct disposal..................................................................... 217 4.5.1.1 The Spanish repository concept................................................................. 217 4.5.1.2 The Swedish repository concept........................................................ 220 4.5.1.3 Performance assessment of spent fuel disposal in clay....................... 222 4.5.2 RFC concepts for disposal............................................................................... 223 4.5.2.1 Disposal in salt formations ............................................................... 223 4.5.2.2 Disposal in clay formations .............................................................. 225 4.5.3 AFC-specific waste management issues (targets, reactor cores)........................ 227 4.6 Criticality safety ...................................................................................................229 5. COMMENTARY ON EXISTING P&T SYSTEMS STUDIES............................................................ 231 5.1 First generation systems study reports ......................................................................... 231 5.2 Second generation reports ........................................................................................... 232 REFERENCES................................................................................................................................ 235 7
Page 1 and 2: TABLE OF CONTENTS EXECUTIVE SUMMARY
Page 3 and 4: TABLE DES MATIÈRES NOTE DE SYNTHÈ
Page 5: PART II. TECHNICAL ANALYSIS AND SYS
Page 9 and 10: Figure II.31 Evolution of the expec
Page 11 and 12: Part II: Technical analysis and sys
Page 13 and 14: There are several scenarios which c
Page 15 and 16: eactor concepts are still in the co
Page 17 and 18: intermediate storage management, th
Page 20 and 21: 1. INTRODUCTION 1.1 Involvement of
Page 22: and natural decay play an important
Page 25 and 26: Figure I.2 A schematic diagram of b
Page 27 and 28: Instead of recycling, one could ado
Page 29 and 30: to address there is the separation
Page 31 and 32: improvement of the biological shiel
Page 33 and 34: Figure I.3 A schematic diagram of t
Page 35 and 36: Figure1.5 A notional materials flow
Page 37 and 38: A few specific regulatory and safet
Page 39 and 40: • irradiation of FR-fuel in Fast
Page 41 and 42: dispersion in the geosphere or bios
Page 43 and 44: In the meantime the burn-up of spen
Page 45 and 46: Any reprocessing campaign of spent
Page 48 and 49: 4. CRITICAL EVALUATION • P&T may
Page 50: 5. GENERAL CONCLUSIONS • Fundamen
Page 54 and 55: NOTE DE SYNTHÈSE ET PORTÉE DU RAP
Page 56 and 57:
Présentation générale Cette part
Page 58 and 59:
courts. L’application de cette te
Page 60 and 61:
éalisable, à condition d’augmen
Page 62:
PREMIÈRE PARTIE : PRÉSENTATION G
Page 65 and 66:
La troisième réunion internationa
Page 67 and 68:
1.5 Objectifs du rapport Dans l’e
Page 69 and 70:
Figure I.1 Schéma de principe du c
Page 71 and 72:
• l ’241 Am est le précurseur
Page 73 and 74:
plutonium et environ 2 m 3 de déch
Page 75 and 76:
2.3 Technologie de fabrication des
Page 77:
cadre de la coopération EFTTRA ont
Page 80 and 81:
On peut voir sur la Figure I.4 les
Page 82 and 83:
Figure I.4 Flux de matières dans u
Page 84 and 85:
À court terme, les produits de fis
Page 86 and 87:
Par conséquent, au cas où l’on
Page 88 and 89:
De nombreux laboratoires dans le mo
Page 90 and 91:
usé devrait représenter environ 3
Page 92 and 93:
le nucléide le plus gênant est le
Page 94 and 95:
transuraniens. Pour obtenir un taux
Page 96 and 97:
On peut considérer des opérations
Page 98 and 99:
devrait en principe ouvrir de nouve
Page 101:
5. CONCLUSIONS GÉNÉRALES • La m
Page 105:
PART II: TECHNICAL ANALYSIS AND SYS
Page 108 and 109:
1.1.1.1 Minor actinides Americium a
Page 110 and 111:
thus preventing its dispersion in t
Page 112 and 113:
By contrast, information about the
Page 114 and 115:
DIDPA [5] (see Figure II.3) process
Page 116 and 117:
The generation of secondary effluen
Page 118 and 119:
Figure II.5 TRPO process TRPO solve
Page 120 and 121:
According to Jarvinen et al. in LAN
Page 122 and 123:
curium. • Separation of americium
Page 124 and 125:
1.1.4.4 Separation of technetium an
Page 126 and 127:
The second option is production of
Page 128 and 129:
Figure II.9 Fuel cycle actinide bur
Page 130 and 131:
Figure II.11 Flow sheet of pyro-rep
Page 132 and 133:
The metathetical reaction between L
Page 134 and 135:
This is confirmed by the radiotoxic
Page 136 and 137:
For the same burn-up as in the pure
Page 138 and 139:
planned for a burn-up range of 1.5
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On the basis of the study, it is no
Page 142 and 143:
In a given reactor system, the diff
Page 144 and 145:
- deterioration of the effectivenes
Page 146 and 147:
Table II.5 Mass balances for homoge
Page 148 and 149:
manufacture is 2 years. 12×24 targ
Page 150 and 151:
Figure II.14 MA-loading methods in
Page 152 and 153:
Table II.7 Mass balances for homoge
Page 154 and 155:
Table II.8 Mass balances for hetero
Page 156 and 157:
Core characteristics above: The fol
Page 158 and 159:
Figure II.15 Concept of double stra
Page 160 and 161:
Figure II.16 Concept of accelerator
Page 162 and 163:
In Reference [99], the sodium coole
Page 164 and 165:
In Germany, some small activities r
Page 166 and 167:
OECD/NEA programmes The OECD/NEA Nu
Page 168 and 169:
As a part of MA nuclear data evalua
Page 170 and 171:
Table II.13 Pu and minor actinide b
Page 172 and 173:
2.4.1.3 Transmutation in light wate
Page 174 and 175:
3. DESCRIPTION OF CURRENT TRENDS IN
Page 176 and 177:
The SPIN programme studied various
Page 178 and 179:
• the RP1-2 scenario is compared
Page 180 and 181:
Mass balance The MA mass balance, f
Page 182 and 183:
4. IMPACT OF P&T ON RISK ASSESSMENT
Page 184 and 185:
For deterministic effects, in the c
Page 186 and 187:
• accounting for a number of safe
Page 188 and 189:
Table II.17 Effective dose coeffici
Page 190 and 191:
MOX fuel and recycling of recovered
Page 192 and 193:
Figure II.22 Potential radioactivit
Page 194 and 195:
Moreover, plutonium recycling and m
Page 196 and 197:
Curium is assumed to be stored for
Page 198 and 199:
Figure II.25 shows the radiotoxicit
Page 200 and 201:
decrease is obtained in the radioto
Page 202 and 203:
4.4 Risk and hazard assessment over
Page 204 and 205:
4.4.2 Radiological impact of waste
Page 206 and 207:
0.191 man-Sv/TWhe and the RFC with
Page 208 and 209:
• conventional reprocessing does
Page 210 and 211:
The maximum inventory of reactor co
Page 212 and 213:
pursued. Since 137 Cs and 90 Sr are
Page 214 and 215:
Figure II.26 Surface facilities. Ge
Page 216 and 217:
Doses are controlled by 36 Cl up to
Page 218 and 219:
Figure II.30 Overview of the canist
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surface. The reference repository i
Page 222 and 223:
Figure II.34 Cavern-convection scen
Page 224 and 225:
Figure II.36 Normal evolution scena
Page 226 and 227:
considerable energy release as a re
Page 228 and 229:
• taking into account the potenti
Page 230 and 231:
• on the subject of transmutation
Page 232 and 233:
[12] Arnaud-Neu, F., et al., “Cal
Page 234 and 235:
Fuel”, Proc. Int. Conf. on Future
Page 236 and 237:
[64] Arai, T., Suzuki, Y., Handa, M
Page 238 and 239:
[88] Murata, H., and Mukaiyama, T.,
Page 240 and 241:
[117] Gudowski, W., “Accelerator-
Page 242 and 243:
[146] D’angelo, A., Marimbeau, P.
Page 244 and 245:
[172] OECD/NEA and IAEA, Uranium: R
Page 246:
[202] Schmidt, E., Zamorani, E., Ha
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