This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part II of the series describes component aging aspects and future trends. The component aging aspects include evaluation methods for vessels based on elastic-plastic fracture mechanics, environmental fatigue evaluation guidelines and inspection and evaluation guidelines for reactor internals. With respect to future trends, the development of the International Thermonuclear Experimental Reactor code and the System-Based Code are introduced.
Issue Section:Research Papers
Keywords:nuclear facility regulation, fatigue, fracture mechanics, pressure vessels, fission reactor design, fission reactor materials, flaw detection, fission reactor monitoring, ageing, elastoplasticity
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).
JEAC, 1991, “
Method of Verification Tests of the Fracture Toughness for Nuclear Power Plant Components,” JEAC 4206–1991, Japan Electricity Association (in Japanese).
Asada, 2001, “
Ductile Crack Growth Behavior of a Pressure Vessel With Low Upper Shelf Energy,” ASME PVP
426, Operations, Applications and Components, pp.
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.
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.
Maeda, 2003, “
Simplified J-Integral Evaluation Method for Evaluation of Reactor Pressure Vessel in the Upper-Shelf Region,” ASME PVP
459, Design and Analysis Methods and Fitness-for-Service Evaluations for Pressure Vessels and Components, pp.
ASME, Boiler and Pressure Vessel Code Sec. XI, Appendix A, 2001, “
Analysis of Flaws,” ASME, New York.
Tomimatsu, 2003, “
Development of Prediction Equations on Charpy Upper Shelf Energy for Japanese RPV Steels,” ASME PVP
468, Aging Management and Component Analysis, pp.
Sakaguchi, 2001, “
Comparison of Japanese MITI Guidelines and Other Methods for Evaluation of Environmental Fatigue Life Reduction,” ASME PVP
419, Pressure Vessels and Piping, Codes and Standards 2001.
Thermal and Nuclear Power Engineering Society, 2002, “
Guidelines on Environmental Fatigue Evaluation for LWR Components,” (translated into English).
Asada, 2003, “
Guidelines on Environmental Fatigue Evaluation for LWR Components,” ASME PVP
453, Pressure Vessels and Piping Codes and Standards 2003,
Sakaguchi, 2004, “
Evaluation of Fatigue Damage on Operating Plant Components in LWR Water,” ASME PVP
480, Pressure Vessels and Piping Codes and Standards 2004,
Sakaguchi, 2002, “
A Proposal of Fatigue Life Correction Factor Fen for Austenitic Stainless Steels in LWR Water Environments,” ASME PVP
439, Pressure Vessels and Piping Codes and Standards 2002,
Thermal and Nuclear Power Engineering Society, 2003, “
Inspection and Evaluation Guidelines for Reactor Internals of Boiling Water Reactor (Core Shroud),” (2nd edition).
Tsunematsu, 2000, “
Safety Activities in JAERI Related to ITER,”
IAEA Technical Committee Meeting on Fusion Safety, held in
Tada, 2002, “
Code of a Tokamak Fusion Energy Facility ITER,”
Proceedings of the 10th International Conference on Nuclear Engineering, ICONE 10–22673.
Ueda, 2002, “
System Based Code—Principal Concept,”
Proceedings of the 10th International Conference on Nuclear Engineering, ICONE10—22730.
Ueda, 2002, “
System Based Code—Basic Structure,”
Proceedings of the 10th International Conference on Nuclear Engineering, ICONE10–22731.
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by American Society of Mechanical Engineers