• NUCLEAR TECHNIQUES
  • Vol. 46, Issue 6, 060601 (2023)
Yusheng LIU1、2, Sichao TAN1、*, Jianping JING2, Shaoxin ZHUANG2, Dongyang LI1, and Nan WANG3
Author Affiliations
  • 1Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, Harbin Engineering University, Harbin 150001, China
  • 2Nuclear and Radiation Safety Center, Beijing 100086, China
  • 3State Nuclear Power Technology R&D Center Co., Ltd., Beijing 102209, China
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    DOI: 10.11889/j.0253-3219.2023.hjs.46.060601 Cite this Article
    Yusheng LIU, Sichao TAN, Jianping JING, Shaoxin ZHUANG, Dongyang LI, Nan WANG. Investigation on natural circulation phenomena of LOCA with PRHR pipeline break in ACME facility[J]. NUCLEAR TECHNIQUES, 2023, 46(6): 060601 Copy Citation Text show less
    References

    [1] Zheng M G, Yan J Q, Jun S T et al. The general design and technology innovations of CAP1400[J]. Engineering, 2, 97-102(2016).

    [2] Schulz T L. Westinghouse AP1000 advanced passive plant[J]. Nuclear Engineering and Design, 236, 1547-1557(2006).

    [3] YUAN Tianhong, YU Lei, WANG Chuan. Research on passive residual heat remove system under loss of power[J]. Atomic Energy Science and Technology, 44, 248-252(2010).

    [4] Zou J, Li Q, Tong L L et al. Assessment of passive residual heat removal system cooling capacity[J]. Progress in Nuclear Energy, 70, 159-166(2014).

    [5] Yonomoto T, Kukita Y, Schultz R R. Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments[J]. Nuclear Technology, 124, 18-30(1998).

    [6] Wright R F. Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility[J]. Nuclear Engineering and Technology, 39, 287-298(2007).

    [7] Wang W W, Su G H, Tian W X et al. Research on thermal hydraulic behavior of small-break LOCAs in AP1000[J]. Nuclear Engineering and Design, 263, 380-394(2013).

    [8] Ge J, Tian W X, Qiu S Z et al. CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX)[J]. Nuclear Engineering and Design, 327, 139-149(2018).

    [9] HAO Botao, WANG Nan, ZHONG Jia et al. Analysis of effect of SBLOCA before and behind isolation valve of PRHRS on passive reactor core cooling system[J]. Atomic Energy Science and Technology, 54, 2073-2080(2020).

    [10] LIU Yusheng, XU Chao, WU Peng et al. Experimental Study on sensitivity of PRHR pipeline break location on ACME test facility[J]. Nuclear Power Engineering, 42, 64-70(2021).

    [11] Li Y Q, Chang H J, Ye Z S et al. Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient[J]. Progress in Nuclear Energy, 88, 375-397(2016).

    [12] FANG Fangfang, YANG Fuming, HAO Botao et al. Experimental and numerical analyses of typical SBLOCAs on advanced core-cooling mechanism experiment[J]. Atomic Energy Science and Technology, 51, 1393-1399(2017).

    [13] LIU Yusheng, XU Chao, FANG Fangfang et al. Test study of station blackout accident on advanced core-cooling mechanism experiment facility[J]. Atomic Energy Science and Technology, 52, 1438-1444(2018).

    [14] SHI Guobao, XU Caihong, YAN Jinquan et al. Analysis on key phenomena of CAP1400 passive core cooling integral testing[J]. Atomic Energy Science and Technology, 55, 1806-1813(2021).

    [15] Yang J, Wang W W, Qiu S Z et al. Simulation and analysis on 10-in. cold leg small break LOCA for AP1000[J]. Annals of Nuclear Energy, 46, 81-89(2012).

    [16] LU Xia, KUANG Bo, KONG Haozheng et al. Scaling analysis and preliminary evaluation of integral effect test facility for SBLOCA[J]. Applied Science and Technology, 46, 80-87(2019).

    [17] Wang W W, Su G H, Qiu S Z et al. Thermal hydraulic phenomena related to small break LOCAs in AP1000[J]. Progress in Nuclear Energy, 53, 407-419(2011).

    [18] Bessette D E, di Marzo M. Transition from depressurization to long term cooling in AP600 scaled integral test facilities[J]. Nuclear Engineering and Design, 188, 331-344(1999).

    Yusheng LIU, Sichao TAN, Jianping JING, Shaoxin ZHUANG, Dongyang LI, Nan WANG. Investigation on natural circulation phenomena of LOCA with PRHR pipeline break in ACME facility[J]. NUCLEAR TECHNIQUES, 2023, 46(6): 060601
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