Scaling analysis of the pressure suppression containment test facility for the small pressurized water reactor

Xinxing Liu; Xiangjie Qi; Nan Zhang; Zhaoming Meng; Zhongning Sun

doi:https://doi.org/10.1016/j.net.2020.08.024

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저자정보: Xinxing Liu (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ) Xiangjie Qi (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ) Nan Zhang (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ) Zhaoming Meng (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ) Zhongning Sun (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제3호

발행연도: 2021.3

수록면: 793 - 803 (11page)

DOI: https://doi.org/10.1016/j.net.2020.08.024

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The small PWR has been paid more and more attention due to its diversity of application and flexibility inthe site selection. However, the large core power density, the small containment space and the rapidaccident progress characteristics make it difficult to control the containment pressure like the traditionalPWR during the LOCA. The pressure suppression system has been used by the BWR since the earlydesign, which is a suitable technique that can be applied to the small PWR. Since the configuration andoperating conditions are different from the BWR, the pressure suppression system should be redesignedfor the small PWR. Conducting the experiments on the scale down test facility is a good choice toreproduce the prototypical phenomena in the test facility, which is both economical and reasonable. Asystematic scaling method referring to the H2TS method was proposed to determine the geometrical andthermohydraulic parameters of the pressure suppression containment response test facility for the smallPWR conceptual design. The containment and the pressure suppression system related thermohydraulicphenomena were analyzed with top-down and bottom-up scaling methods. A set of the scaling criteriawere obtained, through which the main parameters of the test facility can be determined.

#Scaling analysis #Small PWR #Top-down #Bottom-up #H2TS

참고문헌 (24)

참고문헌 신청

Biao Quan / 2014 / Research on suppressant characteristics of suppression containment / Nucl. Power Eng 35(2):114~117

Studsvik, A.B. / 1982 / Energiteknik, Marviken Full-Scale Critical-Flow Tests. Volume22. Results from Test 14. Final Report

H. G. Thoren / 1973 / Full-scale Containment Experiments Performed in the Marviken Power Plant. No. CONF-730304–

Yutaka Kukita / 1983 / The noncondensable gas effects on loss-of-coolant accident steam condensation loads in boiling water reactor pressure suppression pool / Nucl. Technol 63(2):337~346

Jani Laine / 2013 / PPOOLEX Experiments on the Dynamics of Free Water Surface in the Blowdown Pipe

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Xinxing Liu

소속기관 Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering Univ