Application of the Failure Assessment Diagram to the Evaluation of Pressure-Temperature Limits for a Pressurized Water Reactor

The failure assessment diagram approach, an elastic-plastic fracture mechanics procedure based on the J-integral concept, was used in the evaluation of pressure-temperature (P-T) limits for the beltline region of the vessel of a pressurized water reactor. The main objective of this paper is to illus...

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Bibliographic Details
Published in:Journal of pressure vessel technology 1985-05, Vol.107 (2), p.192-196
Main Authors: Yoon, K. K, Bloom, J. M, Pavinich, W. A, Slager, H. W
Format: Article
Language:English
Subjects:
Applications
Applied sciences
Energy
Energy. Thermal use of fuels
Engineering techniques in metallurgy. Applications. Other aspects
Exact sciences and technology
Fission nuclear power plants
General, economic and professional studies
Installations for energy generation and conversion: thermal and electrical energy
Joining, thermal cutting: metallurgical aspects
Metals. Metallurgy
Welding
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Summary:The failure assessment diagram approach, an elastic-plastic fracture mechanics procedure based on the J-integral concept, was used in the evaluation of pressure-temperature (P-T) limits for the beltline region of the vessel of a pressurized water reactor. The main objective of this paper is to illustrate the application of an alternate fracture mechanics method for the evaluation of pressure-temperature limits, as allowed by the Code of the Federal Regulation 10 CFR 50, Appendix G. The evaluation of P-T limits for the beltline region of a pressurized water reactor was based on the following assumptions: • ASME Pressure Vessel and Piping Code, Section III, Appendix G reference flaw • End-of-life fluence level in the beltline region • Longitudinal flaw in the beltline weld • J-resistance material toughness curves obtained from the U.S. Nuclear Regulatory Commission’s heavy section steel technology (HSST) program • Other material properties obtained from the Babcock & Wilcox Integrated Reactor Vessel Material Surveillance Program The maximum allowable pressure levels were calculated at 33 time points along the given reactor bulk coolant temperature history representing the normal operation of a pressurized water reactor. The results of the calculations showed that adequate margins of safety on operating pressure for the critical weld in the beltline of the pressurized water reactor vessel are assured.
ISSN:0094-9930
1528-8978
DOI:10.1115/1.3264433