Modeling alternative clad behavior for accident tolerant systems
- 1. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Description
The US Department of Energy Fuel Cycle Research and Development program has a key goal of helping develop accident tolerant fuels (ATF) through investigating fuel and clad forms. In the current work thermochemical modeling and experiment are being used to assess fuel and clad alternatives. Cladding alternatives that have promise to improve fuel performance under accident conditions include the FeCrAl family of alloys and SiC-based composites. These are high strength and radiation resistant alloys and ceramics that have increased resistance to oxidation as compared to zirconium alloys. Accident modeling codes have indicated substantially increased time to failure and resulting effects. In the current work the thermochemical behavior of these materials are being assessed and the work reported here. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)
- Imprint Pagination
- 784 p.
- Journal Page Range
- 3 p.
Conference
- Title
- 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting
- Acronym
- WRFPM 2014
- Dates
- 14-17 Sep 2014
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47079935
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; ALUMINIUM ALLOYS; BWR TYPE REACTORS; CHROMIUM ALLOYS; CLADDING; FUEL CANS; FUEL ELEMENT FAILURE; IRON BASE ALLOYS; OXIDATION; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; SILICON CARBIDES; THERMODYNAMIC PROPERTIES; YTTRIUM ADDITIONS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBIDES; CARBON COMPOUNDS; CHEMICAL REACTIONS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FAILURES; FUELS; IRON ALLOYS; MATERIALS; NUCLEAR FUELS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; SURFACE COATING; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100116.pdf; 12 refs., 6 figs.