Breached oxide blanket fuel behavior in an LMR
- 1. Argonne National Lab., IL (USA)
Description
The run-beyond-cladding-breach (RBCB) behavior of fertile uranium dioxide fuel poses the same questions as that of exposed driver fuel to liquid-metal reactor (LMR) operations and maintenance. If sodium reacts with the blanket fuel, the product may be sufficient to induce cladding loading. This loading, then, has the potential to extend and/or induce cladding failures and degrade overall rod integrity. These open breaches expose fuel or reaction product to sodium and release fission gas, and delayed neutrons, and, potentially, fuel to the primary coolant. These phenomena are being studied as part of a joint program in Experimental Breeder Reactor II (EBR-II) between the US Dept. of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan. Operation of this breached blanket pin caused no operational problems at EBR-II, and the overall consequences of RBCB operation of blanket fuel appears to be benign
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 55
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 290-292
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19106439
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EBR-2 REACTOR; FISSION PRODUCTS; FUEL ELEMENT FAILURE; FUEL INTEGRITY; NONDESTRUCTIVE TESTING; OXIDATION; POST-IRRADIATION EXAMINATION; PRIMARY COOLANT CIRCUITS; REACTOR MAINTENANCE; REACTOR OPERATION; SODIUM; URANIUM DIOXIDE; US DOE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METALS; BREEDER REACTORS; CHALCOGENIDES; CHEMICAL REACTIONS; COOLING SYSTEMS; ELEMENTS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MAINTENANCE; MATERIALS; MATERIALS TESTING; METALS; NATIONAL ORGANIZATIONS; OPERATION; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-8711195--.