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Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water

  • Published:2014-01 Issue:1-3 Volume:444 Page:331-341
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Stephenson Kale J.,Was Gary S.

Funder

Electric Power Research Institute

Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference49 articles.

1. Irradiation-assisted stress-corrosion cracking in austenitic alloys

2. The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors: Phase 2: Commercial Alloys 1009898;Busby,2005

3. The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors: Solute Addition Alloys 1007440;Busby,2003

4. The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors – Phase 3: Deformation Studies 1013081;Busby,2006

5. Characterization of Neutron-Irradiated 300-Series Stainless Steels 1009896;Edwards,2006
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