John Jr, 1978 - Google Patents
Nuclear fuel element leak detection systemJohn Jr, 1978
- Document ID
- 901070950862371246
- Author
- John Jr C
- Publication year
External Links
Snippet
[57] ABSTRACT A leak detection system integral with a wall of a building used to fabricate nuclear fuel elements for detecting radiation leakage from the nuclear fuel elements as the fuel elements exit the building. The leak detecting system comprises a shielded …
- 239000003758 nuclear fuel 0 title abstract description 35
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
-
- 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
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
-
- 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
- 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
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING STRUCTURES OR APPARATUS NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/04—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point
- G01M3/20—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
- G21C17/013—Inspection vehicles
-
- 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
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F7/00—Shielded cells or rooms
-
- 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
- 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
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US20030004390A1 (en) | Transportation vessel for radioactive substance and method of loading closed vessel | |
US3878040A (en) | Failed fuel detector | |
US4117333A (en) | Nuclear fuel element leak detection system | |
US4070240A (en) | Seal containment system | |
US4082607A (en) | Fuel subassembly leak test chamber for a nuclear reactor | |
JPH06300849A (en) | Method for detecting leakage of radioactive gas of nuclear reactor and radioactivity monitor for nuclear reactor | |
US4427893A (en) | Apparatus and method for storing spent fuel assemblies | |
US4828760A (en) | Method of cleaning a spent fuel assembly | |
John Jr | Nuclear fuel element leak detection system | |
KR102372548B1 (en) | Analytical device for detecting fission products by measurement of radioactivity | |
McKinnon et al. | BWR spent fuel storage cask performance test. Volume 1. Cask handling experience and decay heat, heat transfer, and shielding data | |
US5748692A (en) | Rack loader and method for transuranic transfers into and out of storage | |
WO2018135809A1 (en) | Drying apparatus for drying canister for spent nuclear fuel transportation and storage, control method therefor, and radiation shielding geometry for radiation dose rate detector therefor | |
KR810001514B1 (en) | Nuclear fuel element leak detection system | |
Thomas | Preliminary Evaluation of Loading DOE Standardized Canisters in the CPP-603 Irradiated Fuel Storage Facility | |
JPS6020027Y2 (en) | Leak detection device for nuclear fuel rod sealed cans | |
JPS6020026Y2 (en) | Leak detection device for nuclear fuel rod sealed cans | |
Lee et al. | Analysis of Spent Fuel Dry Storage System Work Procedures and Work Patterns | |
Grandjean et al. | How Orano’s experience in high level radioactive materials handling can benefit to Fukushima Daiichi decommissioning program | |
Babilas et al. | Innovative technologies for spent fuel safe management at Ignalina channel-type reactors | |
Kumano | Integrity inspection of dry storage casks and spent fuels at Fukushima Daiichi nuclear power station | |
Borek-Kruszewska et al. | Encapsulation technology of MR6 spent fuel and quality analysis of the EK-10 and WWR-SM spent fuel stored more than 30 years in wet conditions | |
WO2025053854A2 (en) | Fuel handling system, layout, and process for nuclear reactor | |
CN119650126A (en) | High-sealing shielding automatic sample injection system for radioactive sample surface chemical morphology analysis test | |
JPS5991394A (en) | Method of fixing equipment |