Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors

Author:

Kim Jong-Sung,Seo Jun-Min,Kang Ju-Yeon,Jang Youn-Young,Lee Yun-Joo,Kim Kyu-Wan

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference30 articles.

1. ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix G: Fracture Toughness Criteria for Protection against Failure,2019

2. ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section XI, Nonmandatory Appendices, Appendix K: Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact Energy Levels,2019

3. Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events,2006

4. Regulatory Guide 1.154: Format and Content of Plant-specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors;US NRC,1987

5. Structural integrity assessment of aging nuclear reactor pressure vessels;Pennell;Nucl. Eng. Des.,1997

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