Fuel”, Proc. Int. Conf. on Future <strong>Nuclear</strong> Systems: Emerging Fuel Cycles & Waste Disposal Options (Global'93), 12-17 Sept. 1993, Seattle, Washington, Vol. 2, p.1344 (1993). [40] Bychkov, A.V., Vavilov, S.K., Skiba, O.V., Porodonov, P.T., Pravdin, A.K, Popkov, G.P., Suzuki, K., Shoji, Y., Kobayashi, T., “Pyroelectrochemical Reprocessing of Irradiated FBR MOX Fuel. III. Experiment on High Burn-Up Fuel of the BOR-60 Reactor”, Int. Conf. on Future <strong>Nuclear</strong> Systems (Global’97), 5-10 October 1997, Yokohama (Japan), Vol. 2, p.912 (1997). [41] Bychkov, A.V., Skiba, O.V., Porodonov, P.T., Kormilitzin, M.V. and Babikov, L.G., “Development of the Pyroelectrochemical Process for Demonstration Fuel Cycle of an Actinide Burner Reactor”, Int. Conf. on Evaluation of Emerging <strong>Nuclear</strong> Fuel Cycle Systems (Global'95), 11-14 September 1995, Versailles (France), Vol. 1, p. 516 (1995). [42] Inoue, T. and Tanaka, H., “Recycling of Actinides Produced in LWR and FBR Fuel Cycles by Applying Pyrometallurgical Process”, Int. Conf. on Future <strong>Nuclear</strong> Systems (Global’97), 5-10 October 1997, Yokohama (Japan), Vol. 1, p.646 (1997). [43] Chang, Y.I., “The Integral Fast Reactor”, Nucl. Technol., 88, 129 (1989). [44] Tanaka, H., Koyama, M., Iizuka, M., “Development of Pyrometallurgical Reprocessing Technology”, Proc. on the 10th Pacific Basin <strong>Nuclear</strong> Conference, Kobe (Japan), 20-25 October 1996, Vol. 2, p. 1171 (1996). [45] Gay, E.C., Tomczuk, Z. and Miller, W.E., “Plant-Scale Anodic Dissolution of Unirradiated IFR Fuel Pins”, Int. Conf. on Future <strong>Nuclear</strong> Systems: Emerging Fuel Cycles & Waste Disposal Options (Global'93), Seattle, Washington, September 12-17, 1993, Vol. 2, p.1086. [46] Steindler, M.S., et al., Argonne National Laboratory Chemical Technology Division Annual Report 1990, ANL-91/18, p.114 (1991). [47] Kurata, M., Sakamura, Y., Kinoshita, K., Higashi, T., “Separation of Minor Actinides, Rare Earths, Alkali and Alkaline Elements Using Lithium Reduction Process either in LiCl-KCl/Cd or in LiCl-KCl/Bi”, Int. Conf. on Evaluation of Emerging <strong>Nuclear</strong> Fuel Cycle Systems (Global'95), Versailles (France), 11-14 September 1995. [48] Sakamura, Y., Inoue, T., Shimizu, T., Kobayashi, K., “Development of Pyrometallurgical Partitioning Technology of Long-lived Nuclides – Development of Salt Wastes Treatment Technology”, 4th <strong>OECD</strong>/NEA International Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Mito (Japan), September 1996. [49] Lewis, M.A., Fischer, D.F. and Smith, L.I., “Salt-occluded Zeolite as an Immobilization Matrix for Chlorine Waste Salt”, J. Am. Ceram. Soc., 76, 11, p. 2826 (1993). [50] Mukaiyama, T., et al., “Partitioning and Transmutation Program “OMEGA” at JAERI”, International Conference on Evaluation of Emerging <strong>Nuclear</strong> Fuel Cycle, Global’95, September 11-14 1995, Versailles (France), Vol. 1, pp. 110-117. [51] Kobayashi, F., et al., “Anodic Dissolution of Uranium Mononotride in Lithium Chloride-Potassium Chloride Eutectic Melt”, J. Am. Ceram. Soc., 78, pp. 2279-2281 (1995). 240
[52] Akabori, M., et al., “Nitridation of Uranium and Rare-Earth Metals in Liquid Cd”, Proc. Intern. Workshop on Interfacial Effects in Quantum Engineering Systems (IEQES-96), 21-23 Aug. 1996, Mito (Japan), J. Nucl. Mater., 248, pp. 338-342 (1997). [53] Ogawa, T., et al., “Thermochemical Modeling of Actinide Alloys related to Advanced Fuel Cycles”, Proc. the 9th Intern. Symposium on Thermodynamics of <strong>Nuclear</strong> Materials (STNM-9), 25-30 Aug. 1996, Osaka (Japan), J. Nucl. Mater., 247, pp. 215-221 (1997). [54] Maldague, Th., Journet, J., et al., “Reduction of <strong>Nuclear</strong> Waste Toxicity by Actinide Recycling in Fast and Thermal Reactors”, Proc. Int. Conf. on Safe Management and Disposal of <strong>Nuclear</strong> Waste (SAFEWASTE’93), Avignon (France), June 1993. [55] Renard, A., Journet, J., et al., “Actinide Recycling in Fast and Thermal Reactors, a Viable Way to Reduce <strong>Nuclear</strong> Waste Toxicity”, Proc. Int. Conf. on Future <strong>Nuclear</strong> Systems: Emerging Fuel Cycles and Waste Disposal Options (Global’93), Seattle (USA), September 1993. [56] Abrahams, K., Brusselaers, P., et al., Recycling and Transmutation of <strong>Nuclear</strong> Waste, Chapter III.2, <strong>Nuclear</strong> Science and Technology (Final Report), EUR-16750-EN, European Commission, (1996). [57] Haas, D., Lorenzelli, R., et al., “Mixed-Oxide Fuel Fabrication Technology and Experience at the BELGONUCLEAIRE and CFCA Plants and Further Developments for the MELOX Plant”, <strong>Nuclear</strong> Technology, Vol. 106, (April 1994). [58] Renard, A., et al., “Implications of Plutonium and Americium Recycling on MOX Fuel Fabrication”, Proc. Int. Conf. on Evaluation of Emerging <strong>Nuclear</strong> Fuel Cycle Systems, Global’95, Versailles (France), September 1995. [59] Prunier, C., Boussard, F., Koch, L. and Coquerelle, M., “Some Specific Aspects of Homogeneous Am and Np Based Fuels Transmutation Through the Outcomes of the Superfact Experiment in Phenix Fast Reactor”, Proc. Int. Conf. on Future <strong>Nuclear</strong> Systems: Emerging Fuel Cycles and Waste Disposal Options (Global’93), Seattle (USA), September 1993. [60] Hofman, G.L. and Walters, L.C., “Metallic fast reactor fuels”, Materials Science and Technology, A Comprehensive Treatment, Cahn, R.W., Haasen, P., Kramer, E.J. (Eds.), Vol.†10A, <strong>Nuclear</strong> Materials, Part 1, Frost, B.R.T. (Ed.), VCH Verlagsgesellschaft mBH, (1994). [61] Kurata, M., Inoue, T., Sari, C., “Redistribution Behavior of Various Constituents in U-Pu-Zr Alloy and U-Pu-Zr Alloy Containing Minor Actinides and Rare Earths in a Temperature Gradient”, J. Nucl. Mater., 208, 144 (1994). [62] Daumas, S., Lederberger, G., Ingold, F., Bauer, M., Prunier, C., “Nitride Targets Elaborated by Sol-Gel Processing for Actinide Incineration”, Int. Conf. on Evaluation of Emerging <strong>Nuclear</strong> Fuel Cycle Systems, Global’95, Versailles (France), 11-14 Sept. 1995, p. 1638. [63] Ganguly, C., Hegde, P.V., Sengupta, A.K., “Preparation, Characterization and Out-of-Pile Property Evaluation of (U, Pu)N Fuel Pellets”, J. Nucl. Mater., 178, 234 (1991). 241
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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
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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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- Page 232 and 233: [12] Arnaud-Neu, F., et al., “Cal
- 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