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Potential roles for the Master Curve in regulatory application

  • Published:2001-02 Issue:2-3 Volume:78 Page:111-123
  • ISSN:0308-0161
  • Container-title:International Journal of Pressure Vessels and Piping
  • language:en
  • Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Kirk Mark,Mitchell Matthew

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference45 articles.

1. Code of Federal Regulation 10CFR50.61, Fracture toughness requirements for protection against pressurized thermal shock events.

2. SECY-82-465, United States Nuclear Regulatory Commission, 1982.

3. Reactor Vessel Integrity Database, Version 2, United States Nuclear Regulatory Commission.

4. Eason ED, Wright JE, Odette GR. Improved embrittlement correlations for reactor pressure vessel steels, NUREG/CR-6551, 1998.

5. Comparison of irradiation induced shifts of KJc and Charpy impact toughness for reactor pressure vessel steels;Sokolov,1996

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