R & D of oxide dispersion strengthening steels for high burn-up fuel claddings

A. Kimura, H. S. Cho, J. S. Lee, R. Kasada, S. Ukai, M. Fujiwara

Research output: Chapter in Book/Report/Conference proceedingConference contribution

13 Citations (Scopus)

Abstract

Research and development of fuel clad materials for high burn-up operation of light water reactor and super critical water reactor (SCPWR) will be shown with focusing on the effort to overcome the requirements of material performance as the fuel clad. Oxide dispersion strengthening (ODS) steels are well known as a high temperature structural material. Recent irradiation experiments indicated that the steels were quite highly resistant to neutron irradiation embrittlement, showing hardening without accompanying loss of ductility. High Cr ODS steels whose chromium concentration was in the range from 15 to 19wt% showed high resistance to corrosion in supercritical pressurized water (SCPW). As for the susceptibility to hydrogen embrittlement of ODS steels, the critical hydrogen concentration required to hydrogen embrittlement is ranging 10-12 wppm that is approximately one order of magnitude higher value than that of 9Cr reduced activation ferritic (RAF) steel. In the ODS steels, the fraction of helium desorption by bubble migration mechanism was smaller than that in the RAF steel, indicating that the ODS steels are also resistant to helium He bubble-induced embrittlement. Finally, it is demonstrated that the ODS steels are very promising for the fuel clad material for high burn-up operation of water-cooling reactors.

Original languageEnglish
Title of host publicationProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Pages2070-2076
Number of pages7
Publication statusPublished - 2004
Externally publishedYes
EventProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 - Pittsburgh, PA, United States
Duration: 2004 Jun 132004 Jun 17

Publication series

NameProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Other

OtherProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
CountryUnited States
CityPittsburgh, PA
Period04/6/1304/6/17

ASJC Scopus subject areas

  • Engineering(all)

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