Structural Integrity for the RPV of French NPP during the LRA

Abstract:

Most of the French Nuclear Power Plants (NPPs) are currently embarking upon efforts to renew their operating license, while the pressurized thermal shock (PTS) events and environmentally assisted fatigue (EAF) pose potentially significant challenges to the structural integrity of the reactor pressure vessel (RPV) which has the potential to be NPP life-limiting conditions. In the assessment of the PTS events, the deterministic fracture mechanics (DFM) is still used as the basic mechanics in most countries except for the USA. While the maximum nil-ductility-transition temperature (RT_NDT) is about 80°C for 54 French RPVs after 40 years operation, the maximum allowable RT_NDT is only about 70 ^oC and 80 ^oC for the typical PTS events in the IAEA and NEA reports, respectively. On the other hand, the effects of light water reactor (LWR) environmental (other than moderate environment in the code) were not considered in the original design, while the effects of LWR environmental are needed to be considered in the LRA according to the USA regulations. In this paper, the challenges of the PTS and EAF are discussed, and some suggestions are also given for the LRA

• Periodical: Applied Mechanics and Materials (Volume 853)
• Pages: 453-457
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.853.453
• Online since: September 2016
• Authors: Ming Ya Chen*, Wei Wei Yu, Jin Hua Shi, Rong Shan Wang, Lv Feng, Fei Xue, Zhi Lin Chen
• Keywords: EAF, LRA, PTS, Reactor Pressure Vessel, Structural Integrity

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