Experimental Study on Sensitivity of PRHR Pipeline Break Location on ACME Test Facility

Liu Yusheng; Xu Chao; Wu Peng; Wang Nan; Li Zhenxiao

doi:10.13832/j.jnpe.2021.05.0064

Volume 42 Issue 5

Sep. 2021

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Liu Yusheng, Xu Chao, Wu Peng, Wang Nan, Li Zhenxiao. Experimental Study on Sensitivity of PRHR Pipeline Break Location on ACME Test Facility[J]. Nuclear Power Engineering, 2021, 42(5): 64-70. doi: 10.13832/j.jnpe.2021.05.0064

Citation:

Liu Yusheng, Xu Chao, Wu Peng, Wang Nan, Li Zhenxiao. Experimental Study on Sensitivity of PRHR Pipeline Break Location on ACME Test Facility[J]. Nuclear Power Engineering, 2021, 42(5): 64-70. doi: 10.13832/j.jnpe.2021.05.0064

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Experimental Study on Sensitivity of PRHR Pipeline Break Location on ACME Test Facility

doi: 10.13832/j.jnpe.2021.05.0064

Liu Yusheng^{1, 2
,},
Xu Chao²,
Wu Peng^{2
,
,},
Wang Nan³,
Li Zhenxiao¹

1.
Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, 150001, China
2.
National Environmental Protection Key Laboratory for Simulation Analysis and Verification of Nuclear and Radiation Safety Review, Nuclear and Radiation Safety Center, MEE, Beijing, 100082, China
3.
State Nuclear Power Technology R&D Center, Beijing, 102209, China

Received Date: 2020-07-31
Rev Recd Date: 2021-03-10
Publish Date: 2021-09-30

Abstract

Abstract

To study the safety performance of the advanced passive (AP) nuclear power plant (NPP) under passive system failure condition, the experimental study on the loss of coolant from the passive residual heat removal (PRHR) pipeline break is performed by the advanced core-cooling mechanism experiment (ACME) facility, during which the effect of main test sequences and break location on the key parameters in different phases of the accident is analyzed. As demonstrated by the study results, the ACME PRHR pipeline break test sequences, basically same as those for the small-break loss of coolant accident (SBLOCA) of the cold leg, reproduce the safety characteristics in the natural circulation phase of the passive NPP, blowout phase of the automatic depressurization system (ADS) and safety injection (SI) phase of the in-containment refueling water storage tank (IRWST); in the test at different break locations, the passive core cooling system (PXS) can always ensure the water makeup for core and the core active region remains below the mixed liquid level; and the break locations have notable effect on the ACME LOCA accident sequence, initial depressurization rate of reactor coolant system (RCS), PRHR heat exchanger (HX) flow, blowout flow, core level, IRWST SI flow and other parameters, and have little impact on the SI flow of the core makeup tank (CMT) and accumulator (ACC).
- SBLOCA,
- ACME facility,
- Integral effect test,
- PRHR pipeline

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References(19)

References

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