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[172] OECD/NEA and IAEA, Uranium: Resource, Production and Demand, 1997 Edition, OECD/NEA, Paris, 1998. [173] Sources, Effects and Risks of Ionizing Radiation. Annex B: Exposures from Nuclear Power Production, United Nations Scientific Committee on the effects of Atomic Radiation 1988 Report, New York (USA), 1988. [174] Sources and Effects of Ionizing Radiation. Annex B: Exposures from Man-Made Sources, United Nations Scientific Committee on the Effects of Atomic Radiation 1993 Report, New York, 1993. [175] The Safety of the Nuclear Fuel Cycle, OECD-NEA Report, 1993. [176] Recod’94 The Fourth International Conference on Nuclear Fuel Reprocessing and Waste Management, Vol. 1, Session 4 A, London (UK), 24-28 April 1994. [177] Zimmerman, C.H., (BNFL), Private Communication. [178] Baetslé, L.H., “Impact of High Burn-Up Irradiation and Multiple Recycle of Plutonium and Minor Actinides on the Fuel Cycle Activities”, Proceedings of the Third International Information Exchange Meeting on Actinide and Fission Products Partitioning and Transmutation, pp. 40-54, OECD-NEA/P&T N° 13, Cadarache (France), 12-14 December 1994. [179] Long Term Population Dose Due to Radon (Rn-222) Released from Uranium Mill Tailings, prepared for the Uranium Institute by SENES Consultants Limited, April 1998. [180] Externalities of Energy, Report EUR-16520-16524, (1995). [181] Laurent, M., “Recycling of Uranium and Plutonium has No Significant Impact Health or Environmental Impact”, presented at Int. Conf. on Future Nuclear Systems (Global’97), 5-10 Oct. 1997, Yokohama (Japan), (paper not available). [182] Baetslé, L.H., Resumee Atomwirtschaft-Atomtechnik, 4, pp. 260-270 (1993). [183] Baetslé, L.H. and De Raedt, Ch., “Limitations of Actinide Recycle and Fuel Cycle Consequences: a Global Analysis. Part 1: Global Fuel Cycle Analysis”, Nuclear Engineering and Design, Vol. 168, N° 1-3, pp. 191-201 (1997). [184] Viala, M., Salvatores, M. and Mouney, H., “The French Partitioning – Transmutation Programme”, Proc. 4th International Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Mito City (Japan), Sept. 1996, OECD/NEA Report, pp. 60-79 (1997). [185] Baetslé, L.H. and De Raedt, Ch.,”Some Aspects of Risk Reduction Strategy by Multiple Recycling in Fast Burner Reactors of the Plutonium and Minor Actinides Inventories”, Nuclear Engineering and Design, Vol. 172, pp. 197-204 (1997). [186] Uriarte, A., Contribution from ENRESA to OECD/NEA Working Group on P&T (1997). 250
[187] Baetslé, L.H. and De Raedt, Ch., “Limitations of Actinide Recycle and Fuel Cycle Consequences: a Global Analysis. Part 2: Recycle of Actinides in Thermal Reactors”, Nuclear Engineering and Design, Vol. 168, N° 1-3, pp. 203-210 (1997). [188] Wydler, P., et al., “Impact of Transmutation on the Radiotoxicity and Long-Term Risk of the Actinide Waste”, International Conference on the Physics of Reactors, PHYSOR’96 Conference, Mito (Japan), Sept. 1996., Vol. 4, pp. M33-41 (1996). [189] Comparison of the Waste Management Aspects of Spent Fuel Disposal and Reprocessing: Post Disposal Radiological Impact, EUR-13561 Report, European Commission, 1991. [190] Ahlström, P.-E., Contribution from SKB to the OECD /NEA Working Group on P&T (1997). [191] Marivoet, J., Volckaert, G., Snyers, A. and Wibin, J., First Performance Assessment of the Disposal of Spent Fuel in a Clay Layer, EUR-16752 Report, European Commission (1996). [192] Becker, A., Fischer, H., Hofer, E., Kloos, M., Krzykacz, B., Martens, K.H, and Röhlig, K.J., Evaluation of Elements Responsible for the Effective Engaged Dose Rates Associated with the Final Storage of Radioactive Waste: EVEREST Project, Volume 3a: Salt formation, site in Germany, EUR-17449/3a Report, European Commission (1997). [193] Marivoet, J., Performance Assessments of Geological Disposal of High-Level and Medium Level Wastes in the Boom Clay, PACOMA Project (updating 1990), EUR-13042 (1991), European Commission, and, BLG 634, SCK-CEN Report (1992). [194] Marivoet, J., Volckaert, G., Wemaere, I. and Wibin, J., Evaluation of Elements Responsible for the Effective Engaged Dose Rates Associated with the Final Storage of Radioactive Waste: EVEREST project, Volume 2a: Clay Formation, Site in Belgium, EUR-17449/2a Report, European Commission, (1997). [195] SKB: RD&D-Programme 95, p. 78 (1995). [196] Behrenz, P. and Hannerz, K., Criticality in a Spent Fuel Repository in Wet Crystalline Rock, KBS Technical Report 108, (1978). [197] Bowman, C.D. and Venneri, F., Underground Supercriticality from Plutonium an Other Fissile Material, Los Alamos Report, LAUR-94-4022A (1994); also in Science and Global Security, 5, pp. 279 (1996). [198] Compiled by R.A. Konynenburg: Comments on the draft paper “Underground Supercriticality from Plutonium and Other Fissile Material”, Science and Global Security, 5, pp. 303 1996. [199] Ahn, J., “Transport of Weapons-Grade Plutonium and Boron Through Fractured Geologic Media”, Nuclear Technology, 117, pp. 316, March 1997. [200] Claiborne, J.C., Neutron Induced Transmutation of High-Level Radioactive Waste, ORNL-TM-3964 (1972). [201] McKay, H.A.C., et al., The separation and Recycling of Actinides. A Review of the State-of-the-art, EUR 5801, European Commission (1977). 251
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TABLE OF CONTENTS EXECUTIVE SUMMARY
Page 3 and 4:
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
Page 112 and 113:
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
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In Germany, some small activities r
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OECD/NEA programmes The OECD/NEA Nu
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As a part of MA nuclear data evalua
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Table II.13 Pu and minor actinide b
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2.4.1.3 Transmutation in light wate
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3. DESCRIPTION OF CURRENT TRENDS IN
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The SPIN programme studied various
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• the RP1-2 scenario is compared
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Mass balance The MA mass balance, f
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4. IMPACT OF P&T ON RISK ASSESSMENT
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For deterministic effects, in the c
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• accounting for a number of safe
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Table II.17 Effective dose coeffici
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MOX fuel and recycling of recovered
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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
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 246: [202] Schmidt, E., Zamorani, E., Ha
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