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Safety and Engineering Aspects of Spent Fuel Storage Proceedings of an International Symposi... Book

Safety and Engineering Aspects of Spent Fuel Storage Proceedings of an International Symposi...
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  • Safety and Engineering Aspects of Spent Fuel Storage Proceedings of an International Symposi...
  • Written by author Iaea
  • Published by IAEA, 1995/12/31
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Book Categories

Authors

Overview of spent fuel management 3
Dry storage of spent fuel in Argentina: Prospects and technical solutions 15
Spent fuel management in Belgium 29
Canadian spent fuel storage experience 41
Design, planning and siting of spent fuel storage facilities in India 57
Storage facility for BWR spent fuel using casks in Japan 71
Status of the spent fuel management programme in the Republic of Korea 83
Main options for the Romanian spent fuel storage programme 93
Slovak experience with WWER-440 spent fuel storage 103
Development of dual purpose (storage and transport) metal casks in Spain 113
Swedish spent fuel storage programme 121
Spent fuel management and storage in the United States of America 135
The multipurpose canister project 145
The IAEA Co-ordinated Research Programme on the Behaviour of Spent Fuel and Storage Facility Components During Long Term Storage 157
Experience from the operation of the Swedish Central Interim Storage Facility for Spent Nuclear Fuel, CLAB 167
A light water reactor spent fuel receiving and storage facility under construction in China 177
Spent fuel management at the Tsuruga and Tokai-2 power stations 183
Corrosion testing of construction materials of spent WWER-440 fuel 193
Spent fuel storage experience at La Hague 201
Experience of the Societe generale pour les techniques nouvelles in dry vault storage for spent fuel and high level wastes 209
Selection of a spent fuel removal system for THORP as part of the overall spent fuel storage philosophy adopted by British Nuclear Fuels plc 219
Evolution of the MACSTOR dry spent fuel storage system 247
Forged steel casks for the safe and economic storage of irradiated fuel 259
Evaluation of the maximum allowable temperature of WWER-1000 spent fuel under dry storage conditions 269
The first multipurpose spent fuel container reviewed by the United States Nuclear Regulatory Commission 281
Development of advanced spent fuel storage technology at reactor 295
Dry spent fuel storage in Germany: Status in 1994 and prospects 307
Early spent fuel encapsulation for decoupling fuel assembly operation requirements and long term dry storage 321
Licensing of spent fuel storage in Bulgaria: Regulations and problems 331
Licensing of a spent fuel storage facility, including its physical protection, in the Czech Republic 337
Experience with regulatory licensing of spent fuel interim stores: Licence to increase the interim storage capacity of the reprocessing plant ponds at La Hague 347
Dry interim spent fuel storage casks: Licensing, evaluation and operational experience 355
Set of criteria for licensing procedures 369
Safety analysis practices for the dense storage of RBMK spent fuel and improved technology for the long term storage of spent fuel in water pools 377
Licensing process for independent spent fuel storage facilities in Ukraine 389
Summary of the Symposium 395
Characterization of the fuel cladding interface for intermediate and final storage of spent fuel 401
Search for defective fuel assemblies after prolonged storage of spent matrix type fuel 403
Study on changes in radiological conditions after introduction of high density racks in the Angra 2 spent fuel pool 405
Study of an intermediate spent fuel storage facility at the Krsko nuclear power plant site 409
Skoda's experience with spent fuel storage 411
New developments in dry storage casks for spent fuel from RBMK and WWER reactors 413
Interim dry vault storage system for spent fuel 415
Evaluation of heat removal system by natural convection in spent fuel dry storage facilities 418
Development of heavy concrete with depleted uranium 422
Feasibility study of a horizontal dry storage system with overpack 424
Use of tanks equipped with passive systems for residual heat release into the environment to store spent fuel assemblies: Special sites for nuclear power stations 427
An experimental and computational analysis programme for radiation source characterization of MOX and high burnup UOX spent fuel 429
Concept of long term safe storage of leaking RBMK spent fuel in a metal matrix 432
Chairmen of Sessions and Secretariat of the Symposium 435
List of Participants 437
Author Index 449
Index of Papers and Posters by Number 451


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