Preliminary performance evaluation of FeCrAl-ODS steel fuel cladding under accident conditions of BWRs
- 1. Nippon Nuclear Fuel Development Co., Ltd. (NFD), Oarai, Ibaraki (Japan)
- 2. Hokkaido Univ., Sapporo, Hokkaido (Japan)
- 3. Japan Atomic Energy Agency (JAEA), Oarai, Ibaraki (Japan)
- 4. Kyoto Univ., Kyoto (Japan)
- 5. Tokyo Inst. of Technology, Tokyo (Japan)
Description
A preliminary performance evaluation has been performed under accident conditions to compare advantages and disadvantages of application of FeCrAl-ODS steel for the current zirconium-based alloys. Some key material properties of the alloy were also measured for the quantitative evaluations. Under the LOCA condition the FeCrAl-ODS fuel cladding can maintain its mechanical properties beyond the LOCA criteria for the current (zirconium-based alloys) fuel cladding owing to excellent resistances to steam oxidation and thermal shock by water quenching. Moreover, the FeCrAl-ODS fuel cladding can give an additional margin for the fission product release. Under the BDBA condition the FeCrAl-ODS fuel cladding can dramatically reduce the recession rate by both the steam oxidation and the reaction with UO2. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 6 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (Japan); Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49033659
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CLADDING; CRITICAL TEMPERATURE; DESIGN-BASIS ACCIDENTS; FISSION PRODUCT RELEASE; FUEL PELLETS; HEATING RATE; LOSS OF COOLANT; QUENCHING; REACTOR ACCIDENT SIMULATION; REACTOR MATERIALS; TEMPERATURE DEPENDENCE; THERMOCOUPLES; URANIUM DIOXIDE; WATER COOLED REACTORS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; DEPOSITION; MATERIALS; MEASURING INSTRUMENTS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTORS; SIMULATION; SURFACE COATING; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; TRANSITION TEMPERATURE; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17707.pdf; 8 refs., 10 figs.