Study on damage microstructure development of re-welded austenitic stainless steel of in-core component using light-ion irradiation

Shuhei Nogami, Daisuke Koike, Akira Hasegawa, Manabu Satou, Katsunori Abe

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

Abstract

Damage microstructure development including helium (He) bubble formation in solution annealed type 316L austenitic stainless steel due to heat treatment (850 and 1050°C for 5-500 min) after He ion pre-implantation (10-1000 appm) at room temperature and hydrogen (H) ion irradiation (0-0.5 dpa) at the temperature of 300°C after the heat treatment was investigated in order to evaluate the microstructural degradation in a HAZ (heat affected zone) region of in-core components of fission reactors during re-welding and post welding neutron irradiation. The growth of He bubbles was observed due to the increment of He concentration, annealing time and annealing temperature of heat treatment, and displacement damage by H irradiation. He bubbles formed during the heat treatment and after H ion irradiation were distributed both in the grain boundary and in the matrix. The significant growth of He bubbles in the grain boundary after H irradiation up to 0.5 dpa was observed.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Pages1343-1352
Number of pages10
Volume2
Publication statusPublished - 2007 Dec 1
Event13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 - Whistler, BC, Canada
Duration: 2007 Apr 192007 Apr 23

Other

Other13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
CountryCanada
CityWhistler, BC
Period07/4/1907/4/23

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Materials Science(all)

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