Noyes, 1973 - Google Patents
Shipping cask for fast reactor fuel elementsNoyes, 1973
View PDF- Document ID
- 963370094443432966
- Author
- Noyes H
- Publication year
External Links
Snippet
ABSTRACT A weil-shieldcd shipping container weighing approximately 12 500 1b has been designed to accommodate irradiated fuel pins up to 40 in. in length in support of the Liquid Metal Fast Breeder Reactor Program. Having attained a burnup of 10 at.%, with increased …
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
-
- 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
- G21Y2002/104—Inadequate performance, deformation, cracks, rupture
-
- 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
- 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
- G21Y2002/304—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
- G21Y2002/501—Radiation exposure
-
- 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
- G21Y2002/303—Risk of damage
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
- G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Noyes | Shipping cask for fast reactor fuel elements | |
| Noyes | Shipping container for plutonium-238 as fissile material class 1 | |
| DiSabatino et al. | Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings | |
| Johnson et al. | MARVEL Fuel Fabrication Strategy | |
| Anderson et al. | Package Review Guide for Reviewing Safety Analysis Reports for Packages (Revision 4) | |
| Shappert | CASK DESIGNERS GUIDE: A GUIDE FOR THE DESIGN, FABRICATION, AND OPERATION OF SHIPPING CASKS FOR NUCLEAR APPLICATIONS. | |
| Solutions | Safety Analysis Report for Packagings Model 9979 Type AF Shipping Package | |
| Lawrence | Shipping Container for Plutonium-238 as Fissile Material Class | |
| Anderson | Use of filler materials to aid spent nuclear fuel dry storage | |
| Evans et al. | Safety analysis report: packages $ sup 238$ Pu oxide shipping cask (packaging of fissile and other radioactive materials). Final report | |
| DiSabatino et al. | Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2 | |
| Evans et al. | Safety Analysis Report–Packages: LLD-1 Package (Packaging of Fissile and Other Radioactive Materials) | |
| Liu et al. | Certification of SAFESHIELD 2999A | |
| Chung | Safety Analysis Report for Packaging | |
| Fisher et al. | Packaging review guide for reviewing safety analysis reports for packagings: Revision 1 | |
| Canadian Nuclear Safety Commission | RD-364: Joint Canada-United States Guide for Approval of Type B (U) and Fissile Material Transportation Packages | |
| Dekker | Transport of UF6 in compliance with TS-R-1 | |
| O’Connor | Safety Evaluation Report for the | |
| Prosser et al. | Artificial heart heat source program: a summary report | |
| Klima et al. | Analysis of the Oak Ridge National Laboratory foamglas shipping container | |
| Blink et al. | Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems (Rev. 2) | |
| Schively | USER'S GUIDE FOR THE IRRADIATION OF EXPERIMENTS IN THE FTR. | |
| Gates et al. | Safety analysis report UO $ sub 2$ shipping package (packaging of radioactive and fissile materials). Final report | |
| Gomberg et al. | DOEIRW-0351 QA: QA | |
| Meikle | A review of tritium licensing requirements |