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Figure II.26 Surface facilities. General layout Figure II.27 Underground facilities. General layout The repository area needed is 2.58 km 2 for clay, 4.1 km 2 for granite and 1.2 km 2 for salt, and the total excavated rock volume amounts to about 765 000 m 3 for clay, 569 000 m 3 for granite and 579 000 m 3 for salt. 220
The disposal geometry to be selected for a specific repository site must be compatible with the different thermal requirements imposed by the specific medium. The thermal analysis performed recommended a spacing between emplacement drifts of 50 to 100 m for clay, 35 m for granite and 23 m for salt. The length of the waste emplacement drift will be limited to 500 m for practical reasons, with a cross-section of about 5 m 2 and capacity for up to 87 disposal canisters. For adequate buffering, the space between canisters has been fixed at 1 m for granite and salt options, and 2.5 m for a clay option. Once the emplacement activities are finished, all open space inside the repository mine must be backfilled and sealed. Different backfilling materials will be used (in-situ compacted reconstituted clay for the clay option, in-situ compacted mixture of bentonite and sand for the granite option, and insitu compacted crushed salt for the salt option). Filled regions will be isolated from the rest of the emplacement area by means of dedicated seals. The repository area will be isolated by seals in the access shafts. A probabilistic performance assessment for a generic site in a granitic host rock formation has been completed. It has permitted evaluation of the relative importance and performance of the various components of the repository total system as well as a sensitivity analysis of the various parameters. A normal evolution scenario, with appropriate performance ascribed to the designed engineering barriers, has been considered as reference scenario. A hydrogeological regime based on present-day conditions and a reference biosphere has been assumed. Figure II.28 shows the mean dose rates obtained for the normal evolution scenario averaged over 100 simulation runs. A peak dose of 2.36 µSv/year, well below the regulatory limit of 100 µSv/year, is reached 600 000 years after waste disposal, with 129 I responsible for 99% of it. Figure II.28 Evolution of mean dose rates in the case of disposal of 40 GWd/tHM UOX spent fuel 10 -6 Total Mean dose rate (Sv/year) 10 -7 10 -8 10 -9 10 -10 10 -11 10 -12 I-129 10 -5 10 3 10 4 10 5 10 6 Se-79 Pd-107 Sn-126 Cl-36 Ra-226 Cs-135 Th-230 10 -13 Time (year) 221
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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
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Figure II.15 Concept of double stra
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Figure II.16 Concept of accelerator
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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 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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