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[88] Murata, H., and Mukaiyama, T., “Fission Reactor Studies in View of Reactor Waste Programmes”, Atomkernenergi-Kerntech., 45 (1983). [89] Mukaiyama, T., et al., “Importance of Double Strata Fuel Cycle for Minor Actinide Transmutation”, Proc. OECD/NEA 3rd Information Exchange Meeting on P&T, Cadarache (France), (1994). [90] Takizuka, T., et al., “Systems Study on Partitioning and Transmutation at JAERI”, Proc. OECD/NEA 3rd Information Exchange Meeting on P&T, Cadarache (France), (1994). [91] Salvatores, M., et al., “Role of Accelerator-Driven Systems in Waste Incineration Scenarios”, Proc. Int. Conf. on Future Nuclear Systems (Global'97), Yokohama (Japan), Vol. 1, p. 561 (1997). [92] Katsuta, H., et al., “A Continuous Transmutation System for Long-Lived Nuclides with Accelerator-Driven Fluid Targets”, Proc. OECD/NEA 2nd Information Exchange Meeting on P&T, Argonne (France), (1992). [93] Sasa, T., et al., “Conceptual Design Study of Accelerator-Based Transmutation System with Liquid TRU-Alloy Target and Molten-Salt Blanket”, Progress in Nucl. Energy, 29 (1995). [94] Mukaiyama, T., et al., “Minor Actinide Transmutation in Fission Reactors and Fuel Cycle Consideration”, 2nd OECD/NEA Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Argonne (France), (1992). [95] Mukaiyama, T. et al.: “Minor Actinide Transmutation in Fission Reactors and Fuel Cycle Consideration”, 2nd OECD/NEA Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Argonne (France), (1992). [96] Mukaiyama, T. et al.: “Higher Actinide Transmutation using Higher Actinide Burner Reactor”, Proc. Int. Conf. Physics of Reactors, Marseille (France), (1990). [97] Stammbach, Th., et al., “Potential of Cyclotron Based Accelerators for Energy Production and Transmutation”, Proc. Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, Las Vegas (USA), (1994). [98] Wider, H.U., “Basic Safety Features of ADS”, The Status of the Accelerator-Driven System (ADS), IAEA (to be published). [99] Segev, M, et al., “Transmutation of Neptunium, Americium, Technetium, and Iodine in Fast Spectrum Cores Driven by Accelerated Protons”, Nucl. Sci. Engng, 122, pp. 105-120 (1996). [100] Tsujimoto, et al.: “Conceptual Study of the Lead-Bismuth Cooled Accelerator Driven Transmutation System”, to be presented in NuclearApplications of Accelerator Technology (AccApp’98), 20-23 Sept. 1998, Gatlinburg (USA). 244
[101] Sasa, T., et al., “Conceptual Design Study and Code Development for Accelerator-driven Transmutation System”, Int. Conf. on Future Nuclear Systems (Global’97), 5-10 Oct. 1997, Yokohama (Japan), Vol. 1, p.435 (1997). [102] Shibata, K. and Narita, T., Descriptive Data of JENDL-3.2, JAERI-Data/Code 98-006, (1998). [103] Mach, R., “Nuclear Waste Transmutation Program in the Czech Republic”, Proc. Int. Workshop on Nuclear Methods for Transmutation of Nuclear Waste, Dubna, (1996). [104] Viala, M. and Salvatores, M., “The SPIN Program”, International Conference on Evaluation of Emerging Nuclear Fuel Cycle (Global’95), Versailles (France), pp.118-131 (1995). [105] “MUSE Experiments at Cadarache”, Workshop on ADS, Cadarache (France), (1997). [106] Martinez, E., et al., “Spallation Neutron Spectra Measured at SATURNE”, Proc. Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems (Global’95), Versailles (France), pp. 1508 (1995). [107] Trinks, U., “Exotic Cyclotrons – Future Cyclotrons”, Proceedings of Cern Accelerator School: Cyclotrons, Linacs and their Applications, CERN 96-02, (1996) [108] Cazan, A., Schuetz, P. and Trinks, U., “Commissioning of the TRITRON”, International Workshop on RF-Superconductivity, Padua/Albano, (1997). [109] Broeders, I. and Broeders, C.H.M., “Implementation, Development, Validation and First Applications of Different Code Chains for the Investigation of Accelerator Driven Transmutation”, ICENES’96, Obninsk. [110] German contributions in Proceeding of the International Workshop on Nuclear Methods for Transmutation of Nuclear Waste, Dubna, (1996) [111] German contributions in Advanced Nuclear Systems Consuming Excess Plutonium, Merz, E.R. and Walter, C.E. (Eds.), (1996). [112] Napolitano, M., “Research and Industrial Programs on ADS in Italy”, Proceedings of OECD/NEA Workshop on Utilization and Reliability of High-Power Accelerators, Mito (Japan), 13-15 Oct. 1998 (to be published). [113] Takizuka, T. et al., “Conceptual Design Study of Accelerator-Driven Systems for Nuclear Waste Transmutation”, Proc. 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, Kalmar, (1996). [114] Mizumoto, M., “Development of High Intensity Proton Accelerator”, Proc. 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, Kalmar, (1996). [115] Park, W.S., et al., “A Study on the Transmutation Capability of Accelerator Driven System”, Proc. OECD/NEA 4th Information Exchange Meeting on P&T, Mito (Japan), (1996). [116] Kudrayavtsev. E.G., “Analysis of the Preliminary Results of the Russian P&T Research Programme”, IAEA-TECDOC-783, (1995). 245
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
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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
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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
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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
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
Page 96 and 97:
On peut considérer des opérations
Page 98 and 99:
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
Page 188 and 189: 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 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
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