In order to prevent brittle fracture, the pressure and temperature in a reactor pressure vessel (RPV) is controlled by pressure-temperature (P-T) limit curves during the heat-up and cool-down processes. Nuclear power plants should update the P-T limit curves periodically, because of RPV material irradiation embrittlement. Too restricted P-T limit curves may cause difficulty of operating a reactor. The 2007 edition of the RCCM code Annex ZG provides a new method for defining the P-T limit curves. In this paper, two types of the P-T limit curves for a French type RPV are established by different methods, which are the current operation limits based on the 1993 edition of the RCCM code and the new proposed limits according to the 2007 edition of the code. The margins of the current P-T limit curves are evaluated by comparing with the new proposed limit curves. Furthermore, the reasonability of improvements of the new P-T limit curve method is discussed, and their individual effects are investigated, including the conventional defect size, the required material toughness and the stress intensity factor plastic correction. The present results indicate that the current P-T limit curves for the RPV studied are conservative and have about 25∼70 °C margin in the transition temperature range and about 10∼12MPa in the upper shell temperature range, depending on different conditions. The new P-T limit curve method, which not only removes some conservative assumptions in the previous method but also restricts some requirements, is more reasonable and can provide a relaxed operation window. Present results can be a reference for the nuclear power plant owner to release the operation limits and is helpful in enhancing our understanding of the P-T limit curve.
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ASME 2018 Pressure Vessels and Piping Conference
July 15–20, 2018
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5168-5
PROCEEDINGS PAPER
Margins Assessment of Pressure-Temperature Limit Curves for a RPV
Lv Feng,
Lv Feng
Suzhou Nuclear Power Research Institute, Suzhou, China
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Zhou Gengyu,
Zhou Gengyu
Suzhou Nuclear Power Research Institute, Suzhou, China
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Qian Haiyang
Qian Haiyang
GE Power, Windsor, CT
Search for other works by this author on:
Lv Feng
Suzhou Nuclear Power Research Institute, Suzhou, China
Zhou Gengyu
Suzhou Nuclear Power Research Institute, Suzhou, China
Qian Haiyang
GE Power, Windsor, CT
Paper No:
PVP2018-85145, V06BT06A025; 6 pages
Published Online:
October 26, 2018
Citation
Feng, L, Gengyu, Z, & Haiyang, Q. "Margins Assessment of Pressure-Temperature Limit Curves for a RPV." Proceedings of the ASME 2018 Pressure Vessels and Piping Conference. Volume 6B: Materials and Fabrication. Prague, Czech Republic. July 15–20, 2018. V06BT06A025. ASME. https://doi.org/10.1115/PVP2018-85145
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