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Curium is assumed to be stored for a century to allow the 243 Cm and 244 Cm to decay to Pu. This Pu is then recycled with the standard Pu flux. The residual curium (essentially 245 Cm) is recycled with americium in the targets. Only the losses during reprocessing operations are considered with assumptions of 0.1% for Pu and 1% for MAs. 4.3.1.3 Results In terms of installed capacity, the proportions of the different components of the reactor systems at equilibrium are as follows (Table II.18). Table II.18 Recycling mode with varying reactor park composition PWR UO 2 PWR MOX FBR MIX 1 70% – 30% MIX 2 70% 10% 20% FAST – – 100% The radiotoxic inventory, expressed in Sv/TWhe, going to the wastes, and their changes over time are indicated for the different scenarios, and are compared with the radiotoxic inventory resulting from a reactor system with the same capacity consisting exclusively of PWR UO 2 managed in open cycle, i.e. with all the irradiated fuel discharged in the wastes. The reduction of radiotoxic inventory in the wastes are found to be similar for all the scenarios and close to a factor of 100 (Table II.19). Table II.19 Waste radiotoxic inventory reduction factor due to MA recycling as a function of disposal times Time (years) 100 1 000 10 000 100 000 1 000 000 MIX 1 74 72 77 130 82 MIX 2 71 75 84 140 80 FAST 110 100 100 150 150 One important result of all the scenarios examined is that the Pu+MA inventory in the cycle can be stabilised. For each of the systems considered, the mass inventory in the reactors is given in Table II.20. 202
Table II.20 Reactor inventories in different systems (kg/GWe) UO 2 MIX 1 MIX 2 FAST 237 Np 29 73 77 33 238 Pu 239 Pu 240 Pu 241 Pu 242 Pu 20 243 111 75 44 170 762 1 025 223 312 189 757 979 269 376 154 3 396 2 169 275 210 Total Pu 493 2 492 2 570 6 204 241 Am 242m Am 243 Am 242 Cm 243 Cm 244 Cm 245 Cm 13 0.05 10 1.1 0.07 4.6 0.3 252 19 269 8.6 0.5 57 13 246 17 298 8.1 0.4 59 13 259 21 136 8.0 0.9 47 12 Total Cm 6.0 79 81 68 Total actinides 551 3 184 3 289 6 721 At equilibrium the reactor inventories increase by a factor of 6 to 10 when recycling is performed according to the MIX1, MIX2 and FAST scenarios. 4.3.1.4 Influence of non-recycling of curium In the same scenarios, but with all the curium sent to the wastes, the reduction in radiotoxic inventory is significantly decreased. Table II.21 Radiotoxic inventory reduction factor as a function of recycling mode and disposal time without Cm recycling Time (years) 100 1 000 10 000 100 000 1 000 000 MIX 1 10 12 7 96 36 MIX 2 10 11 7 94 32 FAST 21 24 14 115 57 The comparison of the data of Table II.19, with the curium recycling option, to those of Table II.21 with curium discharge in the waste streams, shows that the radiotoxic inventory reduction factor is decreased from the range of 70-150 down to 7-115 depending on the time interval. This obviously has direct repercussions on the radiotoxicity levels in the conditioned high level wastes. Within the time frame of 10 000 years, curium recycling has a significant impact: the ratios between the reduction factors range from 5 to 10. Beyond 10 000 years the impact of curium recycling becomes negligible. 203
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TABLE OF CONTENTS EXECUTIVE SUMMARY
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TABLE DES MATIÈRES NOTE DE SYNTHÈ
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PART II. TECHNICAL ANALYSIS AND SYS
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4. IMPACT OF P&T ON RISK ASSESSMENT
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Figure II.31 Evolution of the expec
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Part II: Technical analysis and sys
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There are several scenarios which c
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eactor concepts are still in the co
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intermediate storage management, th
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1. INTRODUCTION 1.1 Involvement of
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and natural decay play an important
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Figure I.2 A schematic diagram of b
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Instead of recycling, one could ado
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to address there is the separation
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improvement of the biological shiel
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Figure I.3 A schematic diagram of t
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Figure1.5 A notional materials flow
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A few specific regulatory and safet
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• irradiation of FR-fuel in Fast
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dispersion in the geosphere or bios
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In the meantime the burn-up of spen
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Any reprocessing campaign of spent
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4. CRITICAL EVALUATION • P&T may
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5. GENERAL CONCLUSIONS • Fundamen
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NOTE DE SYNTHÈSE ET PORTÉE DU RAP
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Présentation générale Cette part
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courts. L’application de cette te
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éalisable, à condition d’augmen
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PREMIÈRE PARTIE : PRÉSENTATION G
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La troisième réunion internationa
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1.5 Objectifs du rapport Dans l’e
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Figure I.1 Schéma de principe du c
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• l ’241 Am est le précurseur
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plutonium et environ 2 m 3 de déch
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2.3 Technologie de fabrication des
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cadre de la coopération EFTTRA ont
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On peut voir sur la Figure I.4 les
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Figure I.4 Flux de matières dans u
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À court terme, les produits de fis
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Par conséquent, au cas où l’on
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De nombreux laboratoires dans le mo
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usé devrait représenter environ 3
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le nucléide le plus gênant est le
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transuraniens. Pour obtenir un taux
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On peut considérer des opérations
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devrait en principe ouvrir de nouve
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5. CONCLUSIONS GÉNÉRALES • La m
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PART II: TECHNICAL ANALYSIS AND SYS
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1.1.1.1 Minor actinides Americium a
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thus preventing its dispersion in t
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By contrast, information about the
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DIDPA [5] (see Figure II.3) process
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The generation of secondary effluen
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Figure II.5 TRPO process TRPO solve
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According to Jarvinen et al. in LAN
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curium. • Separation of americium
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1.1.4.4 Separation of technetium an
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The second option is production of
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Figure II.9 Fuel cycle actinide bur
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Figure II.11 Flow sheet of pyro-rep
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The metathetical reaction between L
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This is confirmed by the radiotoxic
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For the same burn-up as in the pure
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planned for a burn-up range of 1.5
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On the basis of the study, it is no
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In a given reactor system, the diff
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- 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 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
Page 220 and 221: 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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