An assessment of tensile, irradiation creep, creep rupture, and fatigue behavior in austenitic stainless steels with emphasis on spectral effects-Reference-Cited by-同舟云学术

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An assessment of tensile, irradiation creep, creep rupture, and fatigue behavior in austenitic stainless steels with emphasis on spectral effects

Published:1990-11 Issue:2-3 Volume:174 Page:264-281
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Grossbeck M.L.,Ehrlich K.,Wassilew C.

Publisher

Elsevier BV

Subject

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

Reference53 articles.

1. Calculated Irradiation Response of Materials Using a Fusion-Reactor First-Wall Neutron Spectrum;Gabriel;Oak Ridge National Laboratory, Report ORNL-TM-5956,1977

2. Hydrogen profiles in tokamak fusion reactor first walls

3. Hydrogen transport in stainless steels

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3. Strain Localisation and Fracture of Nuclear Reactor Core Materials;Journal of Nuclear Engineering;2023-05-04

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