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• the RP1-2 scenario is compared with the R3 scenario; as the minor actinide partitioning starts in 2010, Np and Am are stored before being recycled homogeneously or heterogeneously in FRs after 2020; in homogeneous mode, an amount of Np or Am representing 2.50% of the metal mass is mixed with the FR fuel. • the RP2 scenario is similar to the RPl-2 scenario until 2030. CAPRA (Consommation Accrue de Plutonium en Réacteur Rapide) type FRs progressively start operation after 2030. They are still at the preliminary design phase and are dedicated 1500 MWe incinerators loaded with MOX containing 45% of Pu; they transmute Np in homogeneous mode and Am, Tc and I in heterogeneous mode. The fuel and targets are reprocessed with losses of 0.1% for U and Pu, 0.5% for Np, Am and Cm and 10% for Tc and I; Cm is placed in interim storage. 3.2.1.2 Potential radiotoxicity (Figure II.17) Radiotoxicity has been chosen as a measure of the potential detriment of the waste resulting from the different scenarios analysed. The radiotoxicities are assessed for ingestion of all heavy radionuclides and three long-lived fission products ( 99 Tc, 129 I and 135 Cs). Concerning the reference scenario, recycling in FRs (R3 scenario) leads to a larger decrease in radiotoxicity than recycling in PWRs (R2 scenario). The difference in reduction is by a factor larger than 5 for the R2 scenario between 10 4 and 10 5 years due to the recycling of plutonium. In the short period of 10~10 3 years, the radiotoxicity is primarily due to 244 Cm, then to 241 Am. In the long period of 10 3 ~10 5 years, the paramount contributions are from 243 Am, its daughter 239 Pu and from 240 Pu. In the very long period of more than 10 5 years, the radiotoxicity is dominated by 237 Np and the decay products of uranium. The reductions in radiotoxicity for the RP1-1 and RP1-2 scenarios are nearly the same as in the R2 and R3 scenarios respectively. There is an improvement by a factor of 6 between 10 2 and 10 3 years because of the decrease in Am inventory and similarly between 5×10 5 and 5×10 6 years due to the smaller Np content. For short time periods (
Figure II.17 Radiotoxicity balances Waste inventory compared with R1 (-) 1.2 1.0 0.8 0.6 0.4 0.2 R2 R3 RP1-1 RP1-2 RP2 0.0 10 10 2 10 3 10 4 10 5 10 6 10 7 2.5 Time after end of scenario (year) Cycle inventory compared with R1 (-) 2.0 1.5 1.0 0.5 R2 R3 RP1-1 RP1-2 RP2 0.0 10 10 2 10 3 10 4 10 5 10 6 10 7 Time after end of scenario (year) 3.2.2.1 MOX-fuelled FBR [161] Production of minor actinides Minor actinides are produced in the cores of fission reactor (light water reactor and fast reactor) by the neutron absorption and decay reactions. In particular, almost all 241 Am is generated during spent fuel cooling by the β-decay of 241 Pu. A 1 000 MWe-LWR operating for a year discharges 24 tons of spent fuel containing 22.6 tons of uranium, 1 120 kg FPs, 250 kg Pu, and 20 kg MAs. 185
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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
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
Page 140 and 141: 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 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
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
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• taking into account the potenti
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• on the subject of transmutation
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[12] Arnaud-Neu, F., et al., “Cal
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Fuel”, Proc. Int. Conf. on Future
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[64] Arai, T., Suzuki, Y., Handa, M
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[88] Murata, H., and Mukaiyama, T.,
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[117] Gudowski, W., “Accelerator-
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[146] D’angelo, A., Marimbeau, P.
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[172] OECD/NEA and IAEA, Uranium: R
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[202] Schmidt, E., Zamorani, E., Ha
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