- Page 1 and 2: TABLE OF CONTENTS EXECUTIVE SUMMARY
- Page 3 and 4: TABLE DES MATIÈRES NOTE DE SYNTHÈ
- Page 5 and 6: PART II. TECHNICAL ANALYSIS AND SYS
- Page 7 and 8: 4. IMPACT OF P&T ON RISK ASSESSMENT
- Page 9 and 10: Figure II.31 Evolution of the expec
- Page 11 and 12: Part II: Technical analysis and sys
- Page 13 and 14: There are several scenarios which c
- Page 15 and 16: eactor concepts are still in the co
- Page 17 and 18: intermediate storage management, th
- Page 20 and 21: 1. INTRODUCTION 1.1 Involvement of
- Page 22: and natural decay play an important
- Page 25 and 26: Figure I.2 A schematic diagram of b
- Page 27 and 28: Instead of recycling, one could ado
- Page 29 and 30: to address there is the separation
- Page 31 and 32: improvement of the biological shiel
- Page 33 and 34: Figure I.3 A schematic diagram of t
- Page 35 and 36: Figure1.5 A notional materials flow
- Page 37 and 38: A few specific regulatory and safet
- Page 39 and 40: • irradiation of FR-fuel in Fast
- Page 41 and 42: dispersion in the geosphere or bios
- Page 43 and 44: In the meantime the burn-up of spen
- Page 45 and 46: Any reprocessing campaign of spent
- Page 48 and 49: 4. CRITICAL EVALUATION • P&T may
- Page 52: REFERENCES [1] Proceedings: Informa
- Page 55 and 56: • Analyse critique afin de dégag
- Page 57 and 58: Comme les fractions soluble et inso
- Page 59 and 60: les techniques pyrochimiques, même
- Page 61 and 62: Le bilan massique global des actini
- Page 64 and 65: 1. INTRODUCTION 1.1 Activités de l
- Page 66 and 67: pourraient être incinérés. En pr
- Page 68 and 69: 2. ÉTAT ACTUEL ET PERSPECTIVES DES
- Page 70 and 71: l’heure actuelle, des réacteurs
- Page 72 and 73: Le technétium présent sous une se
- Page 74 and 75: moins contraignantes vis à vis du
- Page 76 and 77: 2.3.2 Actinides mineurs Le recyclag
- Page 79 and 80: 3. DESCRIPTION DES CYCLES DU COMBUS
- Page 81 and 82: Figure I.3 Schéma du cycle du comb
- Page 83 and 84: Figure I.5 Flux de matières théor
- Page 85 and 86: La séparation des actinides mineur
- Page 87 and 88: • Retraitement du combustible RNR
- Page 89 and 90: notamment sur les nucléides suivan
- Page 91 and 92: usines de retraitement reçoivent l
- Page 93 and 94: augmentant la concentration relativ
- Page 95 and 96: éussir cette entreprise très oné
- Page 97 and 98: 4. ANALYSE CRITIQUE • Dans l’in
- Page 99: thermalisées de réacteurs rapides
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RÉFÉRENCES [1] Proceedings: Infor
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1. PARTITIONING 1.1 Aqueous separat
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Figure II.1 Behaviour of long-lived
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1.1.2 Improved separation of long-l
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HDEHP Yang et al. of KAERI [6] demo
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Figure II.3 DIDPA process Feed (HNO
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A computer code of the TRUEX proces
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Figure II.6 DIAMEX process Feed sol
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1.1.3.3 Americium/curium separation
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waste because the material used for
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Three phases can be distinguished:
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Figure II.8 Schematic presentation
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This recycling system can be operat
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Figure II.12 Flow sheet of pyrochem
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2. TRANSMUTATION 2.1 Introduction N
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2.2 Target and fuel fabrication tec
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In France, one complete subassembly
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applied to uranium-plutonium mixed
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measured transmutation yields were
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• The neutron consumption of the
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In the presence of minor actinides,
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must be stable under irradiation, f
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2.3.3 Transmutation of minor actini
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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
- Page 237 and 238:
[77] Lelièvre, D., et al., Nuclear
- Page 239 and 240:
[101] Sasa, T., et al., “Conceptu
- Page 241 and 242:
[131] Proceedings of the NEA-NSC Wo
- Page 243 and 244:
[159] Harada, H., et al., “Nuclea
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[187] Baetslé, L.H. and De Raedt,