1. 1) Japan Nuclear Energy Safety Organization, Review Manual for Aging-related Technical Assessment, Neutron Irradiation Embrittlement of Reactor Pressure Vessels, JNES-SS-0507-03 (2009), [in Japanese].
2. 2) The Japan Society of Mechanical Engineers, Codes for Nuclear Power Generation Facilities —Rules on Fitness-for-service for Nuclear Power Plants—, JSME S NA 1-2008 (2008), [in Japanese].
3. 3) Japan Electric Association, Nuclear Standards Committee of JEA, Method of Verification Tests of the Fracture Toughness for Nuclear Power Plants Components, JEAC4206-2007 (2007), [in Japanese].
4. 4) U. S. Nuclear Regulatory Commission, Regulatory Guide 1.154 : Format and Content of Plant Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactor (1987).
5. 5) M. EricksonKirk, M. Junge, W. Arcieri et al., Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61), NUREG-1806 (2006).