Effects of high temperature excursion on mechanical and fatigue properties of nuclear pressure vessel steel during fabrication

Author:

Bulloch J.H.

Publisher

Elsevier BV

Subject

Applied Mathematics,Mechanical Engineering,Condensed Matter Physics,General Materials Science

Reference39 articles.

1. Corrosion fatigue of ASTM 302B steel in high temperature water;Kondo;Corrosion Fatigue (NACE-2),1972

2. The effect of an environment of high temperature primary grade nuclear reactor water on a fatigue crack growth characteristics of A533B class 1 plate and weldment materials;Mager;HSST Technical Report 16, Westinghouse Report WCAP-7776,1971

3. The influence of environment on Fatigue;Bamford;Inst. Mech. Eng.,1977

4. W.H. Bamford, D.M. Moon and L.J. Ceschini, Environmentally assisted crack growth in light water reactor materials, Annual Technical Progress Report Fiscal Year 1981, Westinghouse Electric corporation.

5. W.H. Bamford, D.M. Moon and L.J. Ceschini, Environmentally assisted crack growth in light water reactor materials, Annual Technical Progress Report Fiscal Year 1980, Westinghouse Electric corporation.

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