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Figure I.4 Flux de matières dans un parc électronucléaire mixte de 700 TWh composé de REP et de RNR (étude de cas japonaise) Uranium naturel (U nat ) 11 000 t-U Uranium apprauvi pour fabrication du MOX 144 t-U Enrichissement (UTS) 6 560 000 UTS 2 ans Uranium apprauvi 9 740 t-U Fabrication du MOX 236 t-ML Fabrication 1 100 t-U 1 an Réacteurs RNR 200 TWh Réacteurs REP 500 TWh Transport vers retraitement 216 t-ML Transport vers retraitement 1 220 t-U 2 ans Retraitement 216 t-ML Reprocessing 1 220 t-U 4 ans Pu 78 t-Pu URT apprauvi 134 t-U Enrichissement URT 844 000 UTS 5 ans URT apprauvi 1 000 t-U Pu 14 t-Pu Conversion de l’URT 1 180 t-U Stock stratégique Fabrication de l’URT 174 t-U 6 ans 88
Figure I.5 Flux de matières théorique pour un parc de RNR de 700 TWh (étude de cas japonaise) Uranium apprauvi pour la fabrication du MOX 571 t-U Fabrication du MOX 626 t-U Réacteurs RNR 700 TWh Transport vers retraitement 573 t-ML Retraitement 573 t-ML Stockage du Pu pour d’autres RNR 11 t-Pu URT apprauvi 495 t-U Pu 55 t-Pu 3.2 Aperçu des cycles du combustible et questions annexes 3.2.1 Cycle ouvert Le cycle ouvert est la solution prioritaire qu’ont choisie le Canada, l’Espagne, les États-Unis, la Suède et quelques autres pays. Comme les prix de l’uranium sont actuellement assez bas, cette solution produit l’énergie nucléaire la moins chère. Cependant, elle suppose que l’on ne récupère pas les matières fissiles résiduelles (1 pour cent de Pu et 0.8 pour cent d’ 235 U) ni les matières fertiles ( 238 U) qui subsistent dans le combustible usé. La radiotoxicité potentielle à long terme du combustible nucléaire usé provient essentiellement des actinides qu’il renferme, notamment des nucléides transuraniens (TRU = Pu, Np, Am, Cm… ). Ces éléments constituent un important terme source radiologique dans un dépôt de combustible usé, et cela sur de très longues périodes (des centaines de milliers d’années). Cependant, en raison de l’insolubilité intrinsèque des actinides dans les formations géologiques profondes, les transuraniens peuvent être efficacement confinés. 89
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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
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 50: 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 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 105: PART II: TECHNICAL ANALYSIS AND SYS
Page 108 and 109: 1.1.1.1 Minor actinides Americium a
Page 110 and 111: thus preventing its dispersion in t
Page 112 and 113: By contrast, information about the
Page 114 and 115: DIDPA [5] (see Figure II.3) process
Page 116 and 117: The generation of secondary effluen
Page 118 and 119: Figure II.5 TRPO process TRPO solve
Page 120 and 121: According to Jarvinen et al. in LAN
Page 122 and 123: curium. • Separation of americium
Page 124 and 125: 1.1.4.4 Separation of technetium an
Page 126 and 127: The second option is production of
Page 128 and 129: Figure II.9 Fuel cycle actinide bur
Page 130 and 131: 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
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Moreover, plutonium recycling and m
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Curium is assumed to be stored for
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Figure II.25 shows the radiotoxicit
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decrease is obtained in the radioto
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4.4 Risk and hazard assessment over
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4.4.2 Radiological impact of waste
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0.191 man-Sv/TWhe and the RFC with
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• conventional reprocessing does
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The maximum inventory of reactor co
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pursued. Since 137 Cs and 90 Sr are
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Figure II.26 Surface facilities. Ge
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Doses are controlled by 36 Cl up to
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Figure II.30 Overview of the canist
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surface. The reference repository i
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Figure II.34 Cavern-convection scen
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Figure II.36 Normal evolution scena
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considerable energy release as a re
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• taking into account the potenti
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• on the subject of transmutation
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[12] Arnaud-Neu, F., et al., “Cal
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Fuel”, Proc. Int. Conf. on Future
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[64] Arai, T., Suzuki, Y., Handa, M
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[88] Murata, H., and Mukaiyama, T.,
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[117] Gudowski, W., “Accelerator-
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[146] D’angelo, A., Marimbeau, P.
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[172] OECD/NEA and IAEA, Uranium: R
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[202] Schmidt, E., Zamorani, E., Ha
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