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RÉFÉRENCES [1] Proceedings: Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Mito, Japon, 6-8 nov. (1990), rapport OCDE-AEN. [2] Proceedings: Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Argonne National Laboratory, Argonne, Ill., États-Unis, 11-13 nov. (1992), rapport OCDE-AEN : P&T n° 7. [3] Proceedings: Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, CEA-CADARACHE, France, 12-14 déc. (1994), rapport OCDE-AEN : P&T n° 13. [4] Proceedings: Fourth Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Mito, Japon, 11-13 sept. (1996), rapport OCDE-AEN (1997). [5] Proceedings: Fifth Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Mol, Belgique, 25-27 nov. (1998), rapport OCDE-AEN (1999). [6] Assessment Studies on <strong>Nuclear</strong> Transmutation of Byproduct Actinide, Rapport final, Commission des Communautés européennes, CCR, Ispra, SA/ 1-05-03-83-13, (1983). [7] Croff, A.C., Blomeke, J.O., Actinide Partitioning–Transmutation Program, Rapport final, ORNL 5566 (1980). [8] Conseil supérieur de la sûreté et de l’information nucléaires, Rapport de la Commission CASTAING, Rapport du Groupe de travail sur la gestion des combustibles irradiés, Paris, déc. 1981-nov. 1982. [9] Ramspott, L.D., et al., Impacts of New Developments in Partitioning and Transmutation on the Geological Disposal of High Level Waste in Mined Geologic Repositories, UCRL-ID-109203 (mars 1992). [10] Safety and Environmental Aspects of Partitioning and Transmutation of Actinides and Fission Products, Proc. Techn. Committee Meeting, 29 nov.-2 déc. 1993, IAEA-TECDOC-783, (1995). [11] <strong>Nuclear</strong> Wastes : Technologies for Separation and Transmutation (STATS Committee), National Research Council, National Academy of Sciences, Washington D.C., États-Unis (1995). [12] La gestion du plutonium séparé : les options techniques, OCDE-AEN, Paris (1997). [13] Le combustible au plutonium – Une évaluation, OCDE-AEN, Paris (1989). 109
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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
Page 54 and 55: NOTE DE SYNTHÈSE ET PORTÉE DU RAP
Page 56 and 57: Présentation générale Cette part
Page 58 and 59: courts. L’application de cette te
Page 60 and 61: éalisable, à condition d’augmen
Page 62: PREMIÈRE PARTIE : PRÉSENTATION G
Page 65 and 66: La troisième réunion internationa
Page 67 and 68: 1.5 Objectifs du rapport Dans l’e
Page 69 and 70: Figure I.1 Schéma de principe du c
Page 71 and 72: • l ’241 Am est le précurseur
Page 73 and 74: plutonium et environ 2 m 3 de déch
Page 75 and 76: 2.3 Technologie de fabrication des
Page 77: cadre de la coopération EFTTRA ont
Page 80 and 81: On peut voir sur la Figure I.4 les
Page 82 and 83: Figure I.4 Flux de matières dans u
Page 84 and 85: À court terme, les produits de fis
Page 86 and 87: Par conséquent, au cas où l’on
Page 88 and 89: De nombreux laboratoires dans le mo
Page 90 and 91: usé devrait représenter environ 3
Page 92 and 93: le nucléide le plus gênant est le
Page 94 and 95: transuraniens. Pour obtenir un taux
Page 96 and 97: On peut considérer des opérations
Page 98 and 99: devrait en principe ouvrir de nouve
Page 101: 5. CONCLUSIONS GÉNÉRALES • La m
Page 107 and 108: 1. PARTITIONING 1.1 Aqueous separat
Page 109 and 110: Figure II.1 Behaviour of long-lived
Page 111 and 112: 1.1.2 Improved separation of long-l
Page 113 and 114: HDEHP Yang et al. of KAERI [6] demo
Page 115 and 116: Figure II.3 DIDPA process Feed (HNO
Page 117 and 118: A computer code of the TRUEX proces
Page 119 and 120: Figure II.6 DIAMEX process Feed sol
Page 121 and 122: 1.1.3.3 Americium/curium separation
Page 123 and 124: waste because the material used for
Page 125 and 126: Three phases can be distinguished:
Page 127 and 128: Figure II.8 Schematic presentation
Page 129 and 130: This recycling system can be operat
Page 131 and 132: Figure II.12 Flow sheet of pyrochem
Page 133 and 134: 2. TRANSMUTATION 2.1 Introduction N
Page 135 and 136: 2.2 Target and fuel fabrication tec
Page 137 and 138: In France, one complete subassembly
Page 139 and 140: applied to uranium-plutonium mixed
Page 141 and 142: measured transmutation yields were
Page 143 and 144: • The neutron consumption of the
Page 145 and 146: In the presence of minor actinides,
Page 147 and 148: must be stable under irradiation, f
Page 149 and 150: 2.3.3 Transmutation of minor actini
Page 151 and 152: So, the initial content of minor ac
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whereas the proportion of rare eart
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Table II.9 Irradiation of americium
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Table II.10 Core performance at the
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Table II.11 Reactor design paramete
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Spallation target Reliable nuclear
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Review of the existing projects Act
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Swedish activities [117] Research o
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As regards the fast spectra, result
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Plutonium recycling in MOX with enr
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Transmutation of 99 Tc or 129 I to
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Similar calculations were made for
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In January 1989, the Japanese gover
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As a conclusion, the SPIN studies s
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Figure II.17 Radiotoxicity balances
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Figure II.18 Effect of transmutatio
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At low doses, it is considered that
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This being said, prudence is the wa
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data are not of direct application
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10 17 10 16 10 15 10 14 10 13 Actin
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Figure II.21 Potential radioactivit
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Figure II.23 Radiotoxic inventory o
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Since these reactor systems all hav
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Table II.20 Reactor inventories in
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Table II.22 Masses in wastes (kg/TW
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4.3.2 Impact of separated nuclides
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Some gains can also be made in the
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Aqueous discharge Table II.23 Radio
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The Cm issue is more complex since
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Table II.26 Annual discharge of TRU
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11.4 kg/tHM for UO 2 fuel (factor 3
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The choice of the long-term cut-off
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The disposal geometry to be selecte
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are placed in deposition holes dril
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Figure II.31 Evolution of the expec
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Figure II.33 Evolution of the indiv
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eactions by alternative irradiation
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4.6 Criticality safety Typical LWR
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5. COMMENTARY ON EXISTING P&T SYSTE
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The main conclusions of these US re
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REFERENCES [1] Ozawa, M., et al.,
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and Potassium Ferricyanide”, 4th
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[52] Akabori, M., et al., “Nitrid
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[77] Lelièvre, D., et al., Nuclear
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[101] Sasa, T., et al., “Conceptu
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[131] Proceedings of the NEA-NSC Wo
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[159] Harada, H., et al., “Nuclea
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[187] Baetslé, L.H. and De Raedt,
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