Development of environmental fatigue evaluation method for nuclear power plants in JSME code
- 1. IHI Technology Solutions, Inc., Technical Development Center, Yokohama, Kanagawa (Japan)
- 2. Kansai Electric Power Co., Inc., Osaka (Japan)
- 3. Japan Nuclear Technology Institute, Tokyo (Japan)
Description
Many examinations to evaluate the fatigue life reduction of structural materials of nuclear power plants in water simulating LWR coolants have been carried out. At the same time, the effects of several parameters on the fatigue life reduction have been determined quantitatively, since the first paper was published in Japan. Based on these results, the method to evaluate the fatigue damage for the materials exposed to the LWR coolant was developed. The MITI Guidelines (2000) and the TENPES Guidelines (2002) were issued for evaluating environmental fatigue damage at actual plants. The Environmental Fatigue Evaluation Method (EFEM) for Nuclear Power Plants (JSME S NF 1-2006) was established in the Codes for Nuclear Power Generation Facilities published by the JSME after reviewing the equations for the environmental fatigue life correction factor, Fen, and the evaluation techniques based on the updated knowledge at the time. The EFEM revised version has been drafted by incorporating the updated knowledge and is scheduled to be issued by the end of 2009. This paper introduces the outline of the revised JSME Codes and their technical bases concerning the effects of several parameters on the fatigue life reduction in the LWR coolant environment. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 76
- Journal Issue
- 762
- Journal Page Range
- p. 171-181
- ISSN
- 0387-5008
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41116525
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CARBON STEELS; COOLANTS; CORRECTIONS; CORROSION FATIGUE; DISSOLVED GASES; FATIGUE; FLOW RATE; LEAST SQUARE FIT; LOW ALLOY STEELS; NICKEL BASE ALLOYS; NUCLEAR POWER PLANTS; OXYGEN; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; S-N DIAGRAM; STAINLESS STEELS; STRAIN RATE; SULFUR; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; DIAGRAMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FATIGUE; FLUIDS; GASES; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATHEMATICAL SOLUTIONS; MAXIMUM-LIKELIHOOD FIT; MECHANICAL PROPERTIES; NICKEL ALLOYS; NONMETALS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SOLUTES; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 refs., 25 figs., 3 tabs.