Cagnon et al., 1987 - Google Patents
Design and demonstration of the TN-24 spent fuel cask for dry storage and transportCagnon et al., 1987
View PDF- Document ID
- 6323098758889617558
- Author
- Cagnon R
- Mason M
- Publication year
- Publication venue
- Packaging and Transportation of Radioactive Materials (PATRAM'86): Proceedings of an International Symposium on the Packaging and Transportation of Radioactive Materials
External Links
Snippet
Storage of spent fuel is a common problem for many nuclear power plant operators worldwide. A shortage of space will soon become a reality because spent fuel storage pools, even after ro-racking, are too small for plant lifetimes, which, in turn, are tending increasingly …
- 239000002915 spent fuel radioactive waste 0 title abstract description 6
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
- G21F5/12—Closures for containers; Sealing arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/104—Inadequate performance, deformation, cracks, rupture
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/50—Safety, security and safeguard shortcomings
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/202—Slowness of a process or function
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
- G21Y2004/40—Improving a procedure
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Cagnon et al. | Design and demonstration of the TN-24 spent fuel cask for dry storage and transport | |
Kitcher | Initial Evaluation of Microreactor Disposition Options | |
Johnson Jr et al. | Behavior of spent nuclear fuel and storage system components in dry interim storage. | |
Schneider et al. | Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel | |
Bailey et al. | Wet storage integrity update | |
Stuke et al. | Storage and transport | |
Vitkova et al. | Safety criteria for wet and dry spent fuel storage | |
Morris et al. | Contingency options for the dry storage of Magnox spent fuel in the UK | |
Jobson et al. | Castor® X/32 s—a New Dual-Purpose Cask for the Storage and Transport of Spent Nuclear Fuel | |
Spilker et al. | Description of the German concept of final storage cask | |
Takats | Spent fuel storage practices and perspectives for WWER fuel in Eastern Europe | |
Kamimura | Evaluation of Thermal Creep and Hydride Re-orientation Properties of High Burnup Spent Fuel Cladding under Long Term Dry storage | |
Khaperskaya et al. | Russian Experience and Proposals on Management of Non-Conforming SNF of RBMK Reactors | |
Klein et al. | Transportation cask for bare high burnup spent nuclear fuel | |
Guais | Experience in Plutonium Storage and Transportation | |
Anderson | Studies and research concerning BNFP. Spent fuel disassembly: increasing hot-cell storage capacity at the Barnwell Nuclear Fuel Plant | |
Bader et al. | Transportation Cask for Bare High Burnup Used Nuclear Fuel–16362 | |
Goll | Dry storage assessment of LWR fuel in Germany | |
Saegusa | Long term integrity of spent fuel and construction materials for dry storage facilities | |
Graff Jr et al. | Alternative concepts for dry storage of spent fuel at Morris Operation | |
Vizcaino | Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4 | |
Machiels | US spent fuel research and experience | |
Issard | Materials in the environment of the fuel in dry storage | |
Freire-Canosa | Behaviour of power and research reactor fuel in wet and dry storage | |
Zuloaga | Spent fuel and materials performance in wet and dry storage |