Development of high irradiation resistant and corrosion resistant oxide dispersion strengthened austenitic stainless steels

Takahiro Ishizaki, Yusaku Maruno, Kiyohiro Yabuuchi, Sosuke Kondo, Akihiko Kimura

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The next generation of light water reactors, resource renewable BWR (RBWR), which can be burned trans uranium (TRU) is currently under development at Hitachi. The RBWR requires a high flux of fast neutron for efficient burning of the TRU, which is four times as large as that of the ABWR. Therefore, structural materials require both a high resistance to corrosion and to irradiation. In this study, oxide dispersion strengthened austenitic stainless steels (ODS-ASUS) with high corrosion resistance have been developed. The objective of this research is to evaluate irradiation resistance and SCC susceptibility in a simulated reactor water environment for the ODS-ASUS. The materials were irradiated with 6.4, MeV Fe3+ at 673, K up to 8.0, dpa using the DuET facility at Kyoto University. The creviced bent beam (CBB) test is conducted to assess the SCC susceptibility in the hot water, 288, °C, 8, MPa with a dissolved oxygen of 8, ppm.

Original languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
EditorsDenise Paraventi, Michael Wright, John H. Jackson
PublisherSpringer International Publishing
Pages605-615
Number of pages11
ISBN (Print)9783319672434
DOIs
Publication statusPublished - 2018
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
Duration: 2017 Aug 132017 Aug 17

Publication series

NameMinerals, Metals and Materials Series
VolumePart F9
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/TerritoryUnited States
CityPortland
Period17/8/1317/8/17

Keywords

  • IASCC
  • Ion irradiation test
  • ODS
  • RIS
  • SCC
  • Stainless steel

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