1. The Japan Society of Mechanical Engineers (JSME), 2000, Codes for Nuclear Power Generation Facilities, “Rules on Fitness-for-Service for Nuclear Power Plants” (in Japanese).
2. JEAC, 1991, “Method of Verification Tests of the Fracture Toughness for Nuclear Power Plant Components,” JEAC 4206–1991, Japan Electricity Association (in Japanese).
3. Y.
Urabe
, K.Koyama, K.Hosaka, and Y.Asada, 2001, “Ductile Crack Growth Behavior of a Pressure Vessel With Low Upper Shelf Energy,” ASME PVP 426, Operations, Applications and Components, pp. 35–40.
4. U.S. NRC Regulatory Guide 1.161, 1995, “Evaluation of Reactor Pressure Vessels With Charpy Upper-Shelf Energy Less Than 50ft-lb,” U.S. Nuclear Regulatory Commission.
5. ASME, Boiler and Pressure Vessel Code, Sec. XI, Appendix K, 2001, “Assessment of Reactor Vessels With Low Upper Shelf Charpy Impact Energy Levels,” ASME, New York.