Jobson et al., 2000 - Google Patents
Castor® X/32 s—a New Dual-Purpose Cask for the Storage and Transport of Spent Nuclear FuelJobson et al., 2000
View PDF- Document ID
- 4902192776933474626
- Author
- Jobson G
- Spilker H
- Methling D
- Publication year
- Publication venue
- WM’00 Conference, February
External Links
Snippet
Recently, GNB designed a new dual-purpose forged steel CASTOR® cask for the storage and transport of US PWR fuel. The CASTOR® X/32 S is designed to accept up to 32 PWR fuel elements (a cask for BWR fuel elements will be developed based on the concept of the …
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
- 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
- G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
-
- 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
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
-
- 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
-
- 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
- G21Y2002/201—Inadequate efficiency
-
- 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
- G21Y2004/30—Improving a design
-
- 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
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
-
- 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
- G21Y2002/304—Lack of versatility, compatibility
-
- 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
- G21Y2002/00—PROBLEM
- G21Y2002/50—Safety, security and safeguard shortcomings
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- 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
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactors
- G21C1/04—Thermal reactors; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/07—Pebble-bed reactors; Reactors with granular fuel
-
- 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
- G21F1/00—Shielding characterised by the composition of the materials
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| El-Samrah et al. | Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review | |
| EP3363021B1 (en) | Nuclear waste storage canisters | |
| KR19990082245A (en) | Container for transporting, storing and containing nuclear fuel assemblies | |
| US5612543A (en) | Sealed basket for boiling water reactor fuel assemblies | |
| Jobson et al. | Castor® X/32 s—a New Dual-Purpose Cask for the Storage and Transport of Spent Nuclear Fuel | |
| Janberg et al. | Status of the development of final disposal casks and prospects in Germany | |
| Dickson | Flexibility of the BNFL dry storage systems | |
| Schneider et al. | Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel | |
| Vossnacke et al. | Management of spent fuel from power and research reactors using CASTOR and CONSTOR casks and licensing experience in Germany | |
| Bailey et al. | Wet storage integrity update | |
| Becher | Management of spent fuel from power and research reactors using CASTOR and CONSTOR casks and licensing experience worldwide | |
| Stuke et al. | Storage and transport | |
| Spilker et al. | Description of the German concept of final storage cask | |
| Ross et al. | Used Fuel Testing Transportation Model | |
| Winston | Potential Research and Development Opportunities for Light Water Reactor Spent Nuclear Fuel at INL | |
| Shih et al. | NUHOMS registered-MP197 transport cask | |
| Chung et al. | Operational experience of on-site transport of spent nuclear fuel in Korea | |
| CN120164649A (en) | Spent fuel wet-process transfer device and spent fuel wet-process transfer method | |
| Laug et al. | CASTOR THTR transport/storage casks | |
| Ooms et al. | Dry Storage of the BR3 Spent Fuel in the CASTOR® BR3 Cask | |
| Cagnon et al. | Design and demonstration of the TN-24 spent fuel cask for dry storage and transport | |
| Kishimoto et al. | Design Outline of MSF Transportable Storage Casks for Spent Fuels and The First “Type Approval” Experience in Japan | |
| Funke et al. | CASTORR 1000/19: Development and Design of a New Transport and Storage Cask | |
| Klein et al. | Transportation cask for bare high burnup spent nuclear fuel | |
| Diersch et al. | LOW WEIGHT CASTOR® CASK WITH HIGH CAPACITY FOR TRANSPORT AND STORAGE OF SPENT NUCLEAR FUEL |