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[117] Gudowski, W., “Accelerator-Driven Systems – Survey of the Research Programs in the World”, Proc. Int. Workshop on Nuclear Methods for Transmutation of Nuclear Waste, Dubna, (1996). [118] Wenger, H.U., et al., “Calculation/Experiment Comparisons for 0.6 GeV Proton Irradiations of Uranium and Thorium Thin Targets”, Proc. Int. Conf. on the Physics of Reactors – PHYSOR 96, Mito (Japan), (1996). [119] Wydler, P. and Curti, E., “Closing the Fuel Cycle: Consequences for the Long-Term Risk”, Proc. Int. Conf. on Future Nuclear Systems (Global’97), Yokohama (Japan), p. 201 (1997). [120] Accelerator Production of Tritium, Energy Research Advisory Board US DOE (1990), and Accelerator Production of Tritium, JASONS Report JSR-92-310, (1992). [121] Arthur, E.D., “Introduction to Accelerator-Driven Intense Thermal Neutron Sources – Advantages for Transmutation and Other Applications”, Proc. Specialist Meeting. on Accelerator-Driven Transmutation Technology for Radwaste and Other Applications, Stockholm (Sweden), (1991). [122] Bowman, C.D., “Accelerator-Driven Nuclear Energy Without Long-Term High-Level Waste”, Proc. Specialist Meeting. on Accelerator-Driven Transmutation Technology for Radwaste and Other Applications, Stockholm (Sweden), (1991). [123] Venneri, F. et al., The Physics Design of Accelerator-Driven Transmutation Systems, Proc. Int. Conf. on Evaluation of Emerging Nuclear Fuele Cycle Systems (Global’95), Versaille (France), p. 474, (1995). [124] Carminati, F. et al., An Energy Amplifier for Cleaner and Inexhaustible Nuclear Energy Production Driven by a Particle Beam Accelerator, CERN/AT/93-47 (ET), (1993). [125] Rubbia, C., et al., Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier, CERN/AT/95-44 (ET), (1995). [126] Rubbia, C., et al., A Realistic Plutonium Elimination Scheme with Fast Energy Amplifiers and Thorium-Plutonium Fuel, CERN/AT/95-53, (1995). [127] Rubbia, C., Rubio, J.A., A Tentative Programme Towards a Full Scale Energy Amplifier, CERN/LHC/96-11 (EET), (1996). [128] Andriamonje, S., et al., “Experimental Determination of the Energy Generated in Nuclear Cascades by a High Energy Beam”, Proc. OECD/NEA 3rd Information Exchange Meeting on P&T, Cadarache (France), (1994). [129] Overview of Physics Aspects of Different Transmutation Concepts, NEA/NSC/DOC(94)11 (1994). [130] Takano, H., et.al., “Benchmark problems on transmutation calculation by the OECD/NEA task force on physics aspects of different transmutation concepts”, Proceedings of International Conference on the Physics of Nuclear Science and Technology, Islandia, Long Island NY, USA, October 1998 (to be published). 246
[131] Proceedings of the NEA-NSC Workshop on Utilization and Reliability of High Power Proton Accelerators (to be published). [132] SATIF-4, Shielding Aspects of Accelerators and Irradiation Facilities, 17-18 Sept 1998, OECD Proceedings, (in press). [133] Koning, A., Review of High Energy Data and Model Codes for Accelerator-Based Transmutation, NSC/DOC(92)12 (1992). [134] Results of an International Code Intercomparison for Fission Cross-Section calculations, NEA/NSC/DOC(94)6 (1994). [135] Thick target intermediate energy nuclear reactions, NSC/DOC(95)2 (1995) see also: Sobolevsky, N., Conclusions of International Code Comparison for Intermediate Energy Nuclear Data – Thick Target Benchmark for Lead and Tungsten Report, NSC/DOC(96)15 (1995). [136] Intermediate Energy Nuclear Reactions, Code Comparison results, OECD Document (1994). [137] International Codes and Model Intercomparison for Intermediate Energy Activation Yields, NSC/DOC(97)1 (1997). [138] Intermediate Energy Nuclear Reactions, NEA-NSC Specialists’ Meeting, OECD Document (1994). [139] Nucleon-Nucleus Optical Model up to 200 MeV, Proceedings of a NEA-NSC Specialists Meeting, 13-15 November 1996 at Bruyeres-les-Chatel, France. [140] Nuclear Models to 200 MeV for High-Energy Data Evaluations, NEA WPEC Subgroup 12 Report, NEA/WPEC-12 (1998). [141] Koning, A., et.al., High Energy Nuclear Data Files: From ENDF-6 to NJOY to MCNP, NEA/NSC/DOC(97)8 (1997). [142] NEANSC Working Party on International Evaluation Co-operation; Subgroup 13: Intermediate Energy Data; Final report and recommendations for follow-up, 1998, NEA/WPEC-13. [143] “Accelerator Driven Systems: Energy Generation and Transmutation of Nuclear Waste, Status Report”, IAEA-TECDOC-985, (1997). [144] IAEA benchmark of sub-critical core, to be published. [145] European Commission, Annual Progress Report 1996 on Exploring Innovative Approaches, Reactor Safety, Radioactive Waste Management and Disposal and Decommissioning Research Areas of the Nuclear Fission Safety programme 1994-98, (1997), Report EUR-17852-EN, Office for Official Publications of the European Communities, L-2985 Luxembourg. 247
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
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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
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There are several scenarios which c
Page 15 and 16:
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
Page 27 and 28:
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
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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
Page 65 and 66:
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
Page 94 and 95:
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
Page 190 and 191: MOX fuel and recycling of recovered
Page 192 and 193: 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 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
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