Published April 2017 | Version v1
Miscellaneous

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)

Part of:
Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)

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)

Optional Information

Notes
Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17707.pdf; 8 refs., 10 figs.