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A Study on effective system depressurization during a PWR vessel bottom break LOCA with HPI failure and gas inflow prevention (ROSA-V/LSTF test SB-PV-05)

高圧注入系不作動とガス流入防止を想定したPWR原子炉容器底部破断LOCAに及ぼす効果的減圧操作に関する研究(ROSA-V/LSTF実験SB-PV-05)

鈴木 光弘; 竹田 武司 ; 浅香 英明; 中村 秀夫  

Suzuki, Mitsuhiro; Takeda, Takeshi; Asaka, Hideaki; Nakamura, Hideo

ROSA-V計画における加圧水型原子炉(PWR)の底部計装管小破断冷却材喪失事故(SBLOCA)模擬実験の1つとして、全高圧注入系不作動時のアクシデントマネジメント策と蓄圧注入系からのガス流入防止の効果を検証する実験(SB-PV-05)を実施した。使用装置は大型非定常試験装置(LSTF)で、計装管9本破断を想定し、AM策として蒸気発生器(SG)逃がし弁による定率(-55K/h)減圧と補助給水系の30分間作動を実施した。この結果、炉心露出に至ることなく低圧注入系(LPI)が作動し、長期冷却条件を確保した。AISガス流入を想定した類似SB-PV-03実験に比較して、SBLOCA時のAM策有効性にガス流入防止措置が大変重要であることを示した。

A small break loss-of-coolant accident (SBLOCA) experiment was conducted at the Large Scale Test Facility (LSTF) of ROSA-V program to study effects of accident management (AM) measures on core cooling, which are important in case of total failure of high pressure injection (HPI) system during an SBLOCA at a pressurized water reactor (PWR). The LSTF is a full-height and 1/48 volume-scaled facility simulating a 4-loop Westing-house-type PWR (3423 MWt). The experiment, SB-PV-05, simulated a PWR vessel bottom SBLOCA with a rupture of nine instrument tubes, which is equivalent to 0.18% cold leg break. It is clarified that AM actions with steam generator (SG) depressurization to achieve a primary loop cooling rate at -55 K/h and auxiliary feedwater supply for 30 minutes are effective to avoid core uncovery by actuating the low pressure injection (LPI) system. It is also shown through the comparison with the previous experiment of SB-PV-03 that prevention of non-condensable gas inflow from the accumulator injection system (AIS) is very important to actuate the LPI to achieve adequate core cooling. This report presents experiment results of SB-PV-05 in detail and shows the effects of gas inflow prevention on core cooling through the estimation of primary coolant mass and energy balance in the primary system.

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