Irradiation behavior and thermodynamic properties of metallic fuel
Description
Applicability of metallic U-Pu-Zr fuel to commercial fast reactors is being studied in Japan. This requires evaluation of the integrity of the metallic fuel to be used under severe irradiation conditions of commercial reactors, such as higher coolant temperature and higher burnup. When the high temperature application of the metallic fuel is considered, one of the fuel design limits is elimination of fuel centerline melting. The author presents review on some thermal properties of the fuel alloys for fuel temperature estimation. Another design limit is elimination of liquefaction at the fuel-cladding interface during normal reactor operation. The experiments and analyses to determine the liquefaction condition are summarized, where thermodynamic assessments of the relevant alloy systems play an important role as well as in estimation of the fuel alloy properties. The computer code prediction of the irradiation behavior up to a peak burnup ∼20at % is also presented. This suggests that appropriate estimations of cladding wastage by rare-earth elements and accumulation of non-gaseous fission products are important for the analysis of the metallic fuel performance up to such a high burnup. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875558Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of actinide 2001 international conference
- Imprint Pagination
- 986 p.
- Journal Page Range
- p. 675-681
Conference
- Title
- Actinide 2001 international conference
- Dates
- 4-9 Nov 2001
- Place
- Hayama, Kanagawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51054830
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ALLOY NUCLEAR FUELS; BURNUP; ELECTRON MICROPROBE ANALYSIS; EVALUATION; FAST REACTORS; FISSION PRODUCTS; FUEL-CLADDING INTERACTIONS; IRRADIATION; PERFORMANCE TESTING; PHASE DIAGRAMS; PLUTONIUM; SEMIMETALS; THERMAL CONDUCTIVITY; THERMAL DIFFUSION; URANIUM; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; CHEMICAL ANALYSIS; COMPUTER CODES; DIAGRAMS; DIFFUSION; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; INFORMATION; ISOTOPES; MATERIALS; METALS; MICROANALYSIS; NONDESTRUCTIVE ANALYSIS; NUCLEAR FUELS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TESTING; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 41 refs., 9 figs., 1 tab.; This record replaces 34044888