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ROSA/LSTF experiment on a PWR station blackout transient with AM measures and RELAP5 post-test analysis

PWR全交流電源喪失事象に関するROSA/LSTF実験とRELAP5コードによる実験後解析

竹田 武司; 大津 巌; 与能本 泰介

Takeda, Takeshi; Otsu, Iwao; Yonomoto, Taisuke

An experiment on a PWR station blackout transient with the TMLB' scenario and accident management (AM) measures was conducted using the ROSA/LSTF at Japan Atomic Energy Agency under an assumption of non-condensable gas inflow to the primary system from accumulator tanks. The AM measures proposed in this study are steam generator (SG) secondary-side depressurization by fully opening safety valves in both SGs with the incipience of core uncovery and coolant injection into the secondary-side of both SGs at low pressures. The LSTF test revealed the primary pressure started to decrease when the SG primary-to-secondary heat removal resumed soon after the coolant injection into the SG secondary-side. The primary depressurization worsened due to the gas accumulation in the SG U-tubes after the completion of accumulator coolant injection. The RELAP5 code indicated remaining problems in the predictions of SG U-tube liquid level and primary mass flow rate after the gas ingress.

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