Published April 2017 | Version v1
Miscellaneous

Evaluation on tolerance to failure of ODS ferritic steel claddings at the accident conditions of fast reactors

  • 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
  • 2. Hokkaido University, Faculty of Engineering, Sapporo, Hokkaido (Japan)
  • 3. Kyoto University, Institute of Advanced Energy, Uji, Kyoto (Japan)
  • 4. Tokyo Institute of Technology, Tokyo (Japan)
  • 5. Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)

Description

Tolerance of fast rector fuel elements to failure in the typical accident conditions was evaluated for the oxide-dispersion-strengthened (ODS) ferritic steel claddings that are candidate of the cladding material for advanced fast reactors. The evaluation was based on the cladding creep damage, which was quantified by the cumulative damage fractions (CDFs). It was shown that the CDFs of the ODS ferritic steel cladding were substantially lower than the breach limit of 1.0 in the loss of flow and transient over power conditions until a passive reactor shutdown system is actuated. (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
7 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: 17538.pdf; 11 refs., 12 figs., 1 tab.