Experimental investigation on thermal hydraulic interaction of RCS (reactor coolant system) and containment for intermediate break loss-of-coolant accident (IBLOCA) scenario in ATLAS-CUBE test facility

被引:6
作者
Bae, Byoung-Uhn [1 ,2 ]
Lee, Jae Bong [1 ,2 ]
Park, Yu-Sun [1 ,2 ]
Kim, Jongrok [1 ,2 ]
Kang, Kyoung-Ho [1 ,2 ]
机构
[1] Korea Atom Energy Res Inst, Innovat Syst Safety Res Div, Daejeon, South Korea
[2] Daedeokdaero 989 Beon Gil 111, Daejeon 34057, South Korea
关键词
Integral effect test; Reactor containment; ATLAS-CUBE; Intermediate-break loss-of-coolant accident;
D O I
10.1016/j.pnucene.2022.104156
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In order to experimentally investigate the thermal hydraulic interaction between the reactor coolant system (RCS) and the containment, the integral effect tests were conducted in a test facility, ATLAS-CUBE. Three tests for an intermediate-break loss-of-coolant accident (IBLOCA) were conducted for simulating the break of a cold leg or a direct vessel injection (DVI) nozzle. The effect of the mass/energy (M/E) supply from the break and the asymmetric phenomena inside the containment according to the break simulation position were investigated with considering its impact on the pressure/temperature (P/T) behavior inside the containment. As the test results, both of the RCS and the containment were effectively cooled down during the transient, by activation of the safety injection system and the containment spray system, respectively. The M/E supply from the RCS increased a pressure and a steam-gas mixture temperature of the containment, while a wall condensation on the passive heat sink and a spray injection contributed to cool down the steam-gas mixture. The two-phase flow characteristics of the break flow such as the quality or the subcooling of the liquid phase could highly affect the P/T build-up of the steam-gas mixture in the containment. The ATLAS-CUBE test data in this study will contribute to evaluate the thermal hydraulic safety analysis codes for the RCS and the containment.
引用
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页数:11
相关论文
共 17 条
[1]  
American Nuclear Society, 1973, DRAFT ANS 5 1 N18 5
[2]   Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility [J].
Bae, Byoung-Uhn ;
Lee, Jae Bong ;
Park, Yu-Sun ;
Kim, Jongrok ;
Kang, Kyoung-Ho .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (08) :2477-2487
[3]   Realistic small- and intermediate-break loss-of-coolant accident analysis using WCOBRA/TRAC [J].
Bajorek, SM ;
Petkov, N ;
Ohkawa, K ;
Kemper, RM ;
Ginsberg, AP .
NUCLEAR TECHNOLOGY, 2001, 136 (01) :50-62
[4]  
Choi K.Y, 2014, KAERI/TR-5465/ 2014
[5]  
Ghitiu C, 2019, 18 INT TOP M NUCL RE
[6]  
Hong S.J, 2020, T KOREAN NUCL SOC VI, P17
[7]  
Hydro Korea Nuclear Power Co., 2011, FIN SAF AN REP SHIN
[8]  
Ishigaki M, 2019, 18 INT TOP M NUCL RE
[9]   The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) [J].
Ishii, M ;
Revankar, ST ;
Leonardi, T ;
Dowlati, R ;
Bertodano, ML ;
Babelli, I ;
Wang, W ;
Pokharna, H ;
Ransom, VH ;
Viskanta, R ;
Han, JT .
NUCLEAR ENGINEERING AND DESIGN, 1998, 186 (1-2) :177-211
[10]   Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling [J].
Kang, J. C. ;
Jeong, J. S. ;
Lee, D. H. ;
George, T. L. ;
Lane, J. W. ;
Thomasson, S. G. .
NUCLEAR TECHNOLOGY, 2021, 207 (12) :1851-1864