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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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