Effects of neutron irradiation and thermal aging on mechanical properties of ODS ferritic steels for advanced nuclear systems

Ryuta Kasada, Hang Sik Cho, Naoyuki Okuda, Akihiko Kimura

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

3 Citations (Scopus)

Abstract

Effects of neutron irradiation and thermal aging on the tensile properties and Charpy impact properties of oxide dispersion strengthened (ODS) ferritic steels for advanced nuclear systems were investigated and discussed with the results of microstructural observation. After the neutron irradiation in JMTR, significant hardening after irradiation at 290 and 400 °C as well as thermal aging at 500 °C, while no effect was observed after irradiation at 600 °C. While the irradiation hardening was not accompanied by a reduction of total elongation in tensile tests, Charpy impact energy at room temperature was reduced after the irradiation. The hardening after the irradiation at 400 °C and the aging at 500 °C was probably due to the formation of Cr-rich phases. The irradiation hardening observed in the ODS ferritic steels irradiated at 290 °C was well explained by the formation of dislocation loops.

Original languageEnglish
Title of host publicationSelected, peer reviewed papers from The Sixth Pacific Rim International Conference on Advanced Materials and Processing, PRICM 6
PublisherTrans Tech Publications Ltd
Pages1773-1776
Number of pages4
EditionPART 3
ISBN (Print)0878494626, 9780878494620
DOIs
Publication statusPublished - 2007
Externally publishedYes
Event6th Pacific Rim International Conference on Advanced Materials and Processing, PRICM 6 - Jeju, Korea, Republic of
Duration: 2007 Nov 52007 Nov 9

Publication series

NameMaterials Science Forum
NumberPART 3
Volume561-565
ISSN (Print)0255-5476
ISSN (Electronic)1662-9752

Other

Other6th Pacific Rim International Conference on Advanced Materials and Processing, PRICM 6
CountryKorea, Republic of
CityJeju
Period07/11/507/11/9

Keywords

  • 475 °C embrittlement
  • Advanced nuclear systems
  • Irradiation hardening
  • Oxide dispersion strengthened ferritic steels

ASJC Scopus subject areas

  • Materials Science(all)
  • Condensed Matter Physics
  • Mechanics of Materials
  • Mechanical Engineering

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