Abstract
The reference temperature of pressurized thermal shock (PTS) of the reactor pressure vessel (RPV) for the oldest pressurized water reactor in Korea had been predicted to exceed screening criteria of 10CFR50.61. To cope with this issue, a plant-specific PTS analysis had been performed following the methodology and procedures suggested in Reg. Guide 1.154. In this paper, the details of the plant-specific PTS analysis were described. To quantify the PTS risk of the embrittled RPV, the PTS-significant transient sequences were selected and their frequencies were quantified. Then, thermal hydraulics characteristics of the selected transients were analyzed considering fluid mixing in the downcomer region of RPV. The through-wall cracking (TWC) frequencies of the RPV due to various PTS transients were calculated using the probabilistic fracture mechanics analysis technique. The integrated PTS risk, or the total TWC due to all PTS-significant transient sequences, was lower than the Reg. Guide 1.154 limit during and beyond its design life. Finally, the lessons learned and technical issues found through the analysis are described in detail.
Published Version
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