COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

More documents

Recommendations

Info

In Germany, some small activities related to the application of ADSs for the back-end of the nuclear fuel cycle are in progress since several years [99,109,110,111]. The first main objective was to establish reliable calculation procedures in order to be able to compare ADS capabilities with those of critical reactors. Exploratory ADS investigations have been performed for thermal systems with dispersed fuel in lead coolant at FZJ Juelich and for Phénix like fast systems at FZK Karlsruhe. Italian activity ENEA (Ente per la Nuove Tecnologie l’Energia e l’Ambiente) and INFN (Instituto Nazionale di Fisica Nucleare) set up a basic R&D programme TASCO aiming at the study of physics and technologies needed to design an ADS for nuclear waste transmutation. The programme consists of research subprogrammes on proton accelerator, neutronics, thermal-hydraulic analysis, beam window technology, and material technology and compatibility with Pb and Pb-Bi. An industrial programme was also set up to issue a reference configuration description of a low power ADS prototype [112]. JAERI project, Japan JAERI is carrying out studies on accelerator-driven transmutation systems and development of a high-intensity proton accelerator [113,114] under the Japanese OMEGA Programme. Two types, using respectively solid and a molten-salt fuels have been proposed as dedicated transmuters. Engineering tests for accelerator-driven transmutation are planned under the JAERI proposed Neutron Science Project based on a 1.5 GeV-5.3 mA superconducting linac. Demonstration tests on individual components will be made for a 30-60 MWt integral target/core system and technical feasibility of the window/target assembly will be also tested with a 7 MW beam power. KAERI HYPER programme, Korea KAERI has initiated a study on the transmutation since 1992 [115] and is now setting up a long-term research programme called HYPER on ADSs. KAERI is also trying to launch a programme for the development of a 1 GeV-20 mA multi-purpose linear proton accelerator called KOMAC. Russian activities Several research institutes in Russia are involved in a partitioning and transmutation programme directed by MINATOM [116]. Most of activities relevant to accelerator-driven transmutation are carried out within the framework of ISTC projects. Spanish activities CIEMAT (Centro de Investigaciones Energeticas MedioAmbientales y Tecnologicas) started in 1997 a research programme to investigate the physics of accelerator driven transmutation systems. Also, a private enterprise, LAESA (Laboratorio del Amplificador de Energia), has been created in 1997 to build a laboratory for research, development and demonstration of the Energy Amplifier concept. 170
Swedish activities [117] Research on partitioning and transmutation is mainly supported by the Swedish Nuclear Fuel and Waste Management Co. (SKB). The main activities occur at the Royal Institute of Technology in Stockholm, where physics, safety and other aspects of ADSs are studied. The groups has strong international cooperations and participate in projects supported by EU. The Svedberg Laboratory at Uppsala has recently started a project for cross-section measurements of interest for ADSs. PSI activities, Switzerland The PSI activities in the field of transmutation aim at investigating the potential ADSs with regard to reactor performance and radioactive waste management aspects and at supporting developments for the SINQ spallation neutron source. More specifically, the activities comprise high-current cyclotron development and conceptual design work [97], material technology development work for spallation targets, the experimental validation of models in nucleon-meson transport codes by means of the ATHENA irradiation experiments using actinide targets [118], reactor physics and safety analyses of ADSs, and comparison studies for different reactor types and fuel cycles with emphasis on the impact of alternative transmutation strategies on the long-term risk of the radioactive waste [119]. LANL project, USA LANL is developing a linear accelerator with a beam power of hundreds of MW under the APT (Accelerator Production of Tritium) Programme. The project has had many independent reviews. Their conclusions were positive regarding the accelerator and target technologies, but pointed out the need for an appropriate R&D programme [120]. The LANL ATW programme [121,122] aims at reducing the amount and long time hazard of the spent fuel from US commercial nuclear reactors. The ATW-system would incinerate the TRU waste and transmute selected FPs, such as 99 Tc and perhaps 129 I. The ATW-system is a fast spectrum liquid lead-bismuth cooled device coupled to an APT-class linear proton accelerator. (The accelerator, providing a current of 100 mA and a proton energy of 1 GeV is developed for tritium production, also at LANL). The fuel fabrication and the fuel cycle relies on pyrometallurgical processing. LANL is proposing an experimental programme called LIFT [123]. The experiments will be carried out using 1 MW proton beam at LANSCE on Pb-Bi loop and on a ~5 MWt integral target/blanket. CERN EA project CERN is working on the conceptual design of a so-called Energy Amplifier (EA) and this development may be of use to P&T. The design as originally suggested used a moderated system [124]. The present concept is an oxide fuel, Pb-cooled fast subcritical system driven by a 1 GeV-12.5 mA cyclotron [125]. This system was also proposed as a Pu burner [126]. The first demonstration plant is planned to run with a superconducting linac [127]. The CERN group has performed a high-energy physics experiment associated with the concept [128] on a natural U assembly irradiated by 1-3 GeV proton beam. 171
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 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 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 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
Page 132 and 133: The metathetical reaction between L
Page 134 and 135: This is confirmed by the radiotoxic
Page 136 and 137: For the same burn-up as in the pure
Page 138 and 139: planned for a burn-up range of 1.5
Page 140 and 141: On the basis of the study, it is no
Page 142 and 143: In a given reactor system, the diff
Page 144 and 145: - deterioration of the effectivenes
Page 146 and 147: Table II.5 Mass balances for homoge
Page 148 and 149: manufacture is 2 years. 12×24 targ
Page 150 and 151: Figure II.14 MA-loading methods in
Page 152 and 153: Table II.7 Mass balances for homoge
Page 154 and 155: Table II.8 Mass balances for hetero
Page 156 and 157: Core characteristics above: The fol
Page 158 and 159: Figure II.15 Concept of double stra
Page 160 and 161: Figure II.16 Concept of accelerator
Page 162 and 163: In Reference [99], the sodium coole
Page 166 and 167: OECD/NEA programmes The OECD/NEA Nu
Page 168 and 169: As a part of MA nuclear data evalua
Page 170 and 171: Table II.13 Pu and minor actinide b
Page 172 and 173: 2.4.1.3 Transmutation in light wate
Page 174 and 175: 3. DESCRIPTION OF CURRENT TRENDS IN
Page 176 and 177: The SPIN programme studied various
Page 178 and 179: • the RP1-2 scenario is compared
Page 180 and 181: Mass balance The MA mass balance, f
Page 182 and 183: 4. IMPACT OF P&T ON RISK ASSESSMENT
Page 184 and 185: For deterministic effects, in the c
Page 186 and 187: • 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 238 and 239:
[88] Murata, H., and Mukaiyama, T.,
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
show all

COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

Create successful ePaper yourself

Delete template?

Save as template?