Coupling Experiments and Simulations to Understand Metallic Fuel Behavior
- 1. Department of Materials Science and Engineering, University of Florida, Gainesville, FL, 32611 (United States)
- 2. Idaho National Laboratory, PO Box 1625 MS 6188, Idaho Falls, ID 83415 (United States)
- 3. Department of Mechanical and Nuclear Engineering, Pennsylvania State University, State College, P, 16802 (United States)
Description
The development of metal alloy fuels for minor actinide transmutation in fast reactor systems is of high importance. However, it faces numerous technical challenges such as: i) fuel behavior has to be benign during core off-normal events; ii) fuel has to maintain integrity to high burnup; iii) low minor actinide fabrication loss under remote handling conditions; and iv) fuel has to lend itself to low-loss recycling process. Limited experimental fuel performance data is currently available to support the selection of a fuel type for a transmutation system. Metallic fuels are being considered for application in fast reactor environment due to the high burn-up, high fissile and fertile density capability, inherent safety characteristics, favorable thermal response, and relatively easy recycling process. The uranium-plutonium-zirconium (U-Pu- Zr) based alloys are considered as one of the most promising metallic fuels for such application. In this work, we present results of microstructural characterization of Pu-Zr and U-Pu-Zr alloys and provide much needed linkage between thermal properties and microscopic scale observation. A firm understanding of microstructural evolution in reactor materials is imperative and will lead to deeper understanding of in-reactor degradation behavior, creating a new generation of radiation-resistant materials and fuels with the potential for significant increases in burn-up
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 479-480
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52087845
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOYS; BURNUP; COMPUTERIZED SIMULATION; FAST REACTORS; MICROSTRUCTURE; PERFORMANCE; PLUTONIUM; REACTOR MATERIALS; RECYCLING; REMOTE HANDLING; THERMODYNAMIC PROPERTIES; TRANSMUTATION; URANIUM; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; EPITHERMAL REACTORS; MATERIALS; METALS; PHYSICAL PROPERTIES; REACTORS; SIMULATION; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)