In-situ and ex-situ oxide characterization by synchrotron x-ray (SPring-8) in non-sensitized 316 stainless steel and high temperature water combination

Toshio Yonezawa, Masashi Watanabe, Takahisa Shobu, Tetsuo Shoji

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

Abstract

In-situ and ex-situ oxide characterization was performed using synchrotron X-rays (SPring-8), to investigate the mechanism of stress corrosion cracking (SCC) of a non-sensitized cold worked 316 stainless steel specimen in high temperature water. The refreshed type auto-clave with two diamond windows was originally designed and fabricated to conduct the in-situ measurement in high temperature water using synchrotron X-rays. Chevron notched compact tension type specimens of a non-sensitized cold worked 316 stainless steel were loaded, exposed in simulated BWR water and analyzed using synchrotron X-rays under in-situ and ex-situ conditions. The oxide films and their layered structure near exposed surface were identified by X-rays diffraction and the local stress / strain beneath the oxide films were measured by X-rays diffraction. From these experimental results, the oxidation process for the non-sensitized cold worked 316 stainless steel in high temperature water was characterized, and a new model for the corrosion process of non-sensitized cold worked 316 stainless steel in high temperature water was proposed.

Original languageEnglish
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
PublisherJohn Wiley and Sons Inc.
Pages343-354
Number of pages12
ISBN (Print)9781622761944
Publication statusPublished - 2011 Jan 1
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: 2011 Aug 72011 Aug 11

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume1

Other

Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
CountryUnited States
CityColorado Springs, CO
Period11/8/711/8/11

Keywords

  • Chevron notched specimens
  • Constant penetration depth method
  • Inter-granular stress corrosion cracking
  • Simulated BWR water
  • Skin residual stress
  • Vivisection

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Pollution

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