Applying the Master Curve approach to a JRQ A533B Cl.1 material as part of the surveillance program of two BWR Units

Author:

Hernández Callejas R.,Medina Almazán A.L.,Scibetta M.,Vásquez Belmont S.,Santillán Vergara M.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference40 articles.

1. U.S. NRC 10 CFR 50 Appendix G; Fracture toughness requirements; January 2011.

2. U.S. NRC 10 CFR 50 Appendix H; Reactor vessel material surveillance program requirements.

3. ASME Code Section XI, App G; Fracture toughness criteria for protection against failure; Edition 2010.

4. U.S. NRC Regulatory Guide 1.99 Rev. 2; Radiation embrittlement of reactor vessel materials; May 1988.

5. Technical basis for revision of regulatory guide 1.99: NRC guidance on methods to estimate the effects of radiation embrittlement on the Charpy V-notch impact toughness of reactor vessel materials; 1 October 2007.

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