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• conventional reprocessing does not remove MAs from the HLLW, and Np, Am and Cm constitute the main long-term hazard; • the RFC implies the construction and operation of Pu handling facilities for LWR-MOX and in the future for FR-fuel types; • the reprocessing of LWR-MOX fuel is an issue which has not received a full industrial answer and which would have to be investigated in a long-term waste management programme; • the long-term hazard of the MAs is, beyond 40 000 years, determined by 237 Np; • the construction of a repository for MA-free HLW glass, during the initial phase, is of standard design and construction. The impact of P&T is an improvement of the long-term hazard but it requires additional actinide handling facilities and does not eliminate the necessity of geological disposal: • without reprocessing, P&T cannot be implemented; • partitioning of MAs from HLLW is possibly a first step in the gradual decrease of the radiotoxic inventory of vitrified HLW; • long-term storage of partitioned MAs waste fractions and long-lived fission products will be necessary since special reactors have to be developed for transmutation; • partially “incinerated” or “deactivated” separated actinide or fission product targets will need special preparation and conditioning before disposal; • the risk of contaminating the geosphere will be decreased if the conditioning of the toxic radionuclides is improved (e.g. by using ceramic matrices or improved glass compositions for the separated MAs); • the fraction of radionuclides involved in fuel cycle and waste management activities will shift from mainly disposed materials to mostly stored inventories as shown in Table II.25; • compared to these reactor and facility inventories, the tonnages of waste discharged annually in a reactor park of 100 GWe-0.8 year (= 700 TWhe) are given in Table II.26. Table II.25 Mass of transuranic elements in reactor park (tHM/100 GWe) [184] Elements UO 2 MIX1 MIX2 FAST Np 2.9 7.3 7.7 3.3 Pu 52.2 249.2 257 620 Am 2.3 54 56.1 41.6 Cm 0.6 7.9 8.1 6.8 Total 58 318.4 328.9 671.7 214
Table II.26 Annual discharge of TRU wastes (tHM/100 GWe-0.8 year) [184] Elements UO 2 MIX1 MIX2 FAST Np 1.155 0.021 0.022 0.0056 Pu 22.78 0.076 0.056 0.111 Am 1.152 0.075 0.0798 0.0354 Cm 0.126 0.042 0.040 0.018 Total/year 25.21 0.214 0.198 0.17 Total/30 year 756 6.42 5.94 5.1 On comparing the OTC data in terms of inventory point of view, it is obvious that the amount of spent fuel as “waste” represents world-wide 13 years of operation of a 70 000 tHM repository for 320 GWe park. In the MIX1, MIX2 and FAST options, the equilibrium TRU inventory of the reactor and nuclear facilities amounts to 98% of the total amount of actinides involved in the fuel cycle, and the waste discharged over 30 years becomes very small (
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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
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Table II.5 Mass balances for homoge
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manufacture is 2 years. 12×24 targ
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Figure II.14 MA-loading methods in
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Table II.7 Mass balances for homoge
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Table II.8 Mass balances for hetero
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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 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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