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Effect of coolant water temperature of ECCS on failure probability of RPV

ECCSの冷却材温度がRPVの破損確率に及ぼす影響

勝山 仁哉; 眞崎 浩一; Lu, K.; 渡辺 正*; Li, Y.

Katsuyama, Jinya; Masaki, Koichi; Lu, K.; Watanabe, Tadashi*; Li, Y.

加圧水型原子炉の原子炉圧力容器(RPV)において、非常用炉心冷却系(ECCS)の冷却材の温度が加圧熱衝撃(PTS)事象時のRPVの構造健全性に影響する可能性がある。PTS事象時の熱衝撃の影響を低減することを目的とした緩和措置として、ECCSの冷却水温度を上げることに着目し、国内の代表的な高経年化したPWRプラントを対象に、システム解析コードRELAP5及び確率論的破壊力学(PFM)解析コードPASCAL4を用いた熱水力解析及びPFM解析を実施した。その結果、高圧注入系と低圧注入系(HPI/LPI)の冷却水温度のみを上昇させた場合には破損確率の低減に効果はない。一方、HPI/LPI及び蓄圧系の冷却水温度を上昇させた場合にはRPVの破損確率が大きく低減することを示した。

For reactor pressure vessel (RPV) of pressurized water reactor, temperature of coolant water in emergency core cooling system (ECCS) may have influence on the structural integrity of RPV during pressurized thermal shock (PTS) events. Focusing on a mitigation measure to raise the coolant water temperature of ECCS for aged RPVs in order to reduce the effect of thermal shock due to PTS events, we performed thermal hydraulic analyses and probabilistic fracture mechanics analyses by using RELAP5 and PASCAL4, respectively. From the analysis results, it was shown that the failure probability of RPV was dramatically reduced when the coolant temperature in accumulator as well as high and low pressure injection systems (HPI/LPI) was raised, although raising the coolant temperature of HPI/LPI only did not cause reduction in the failure probability.

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