Experimental and analytical investigation on SMART passive safety systems for three 2-inch SBLOCA tests using SMART-ITL

被引:5
作者
Jeon, Byong Guk [1 ]
Bae, Hwang [1 ]
Kim, Su-Hyeon [1 ,2 ]
Yang, Jin-Hwa [1 ]
Ryu, Sung-Uk [1 ]
Yi, Sung-Jae [1 ]
Park, Hyun-Sik [1 ]
机构
[1] Korea Atom Energy Res Inst, 111 Daedeok Daero 989Beon Gil, Daejeon 34057, South Korea
[2] Korea Inst Nucl Nonproliferat & Control, 1418 Yuseong Daero, Daejeon 34101, South Korea
关键词
Passive safety system; System code; Validation; Integral effect test; SMART; Small modular reactor; INJECTION; PERFORMANCE; ACCIDENT;
D O I
10.1016/j.anucene.2023.109835
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
The SMART-ITL facility is an integral test loop for SMART, a 360 MWt integral type reactor. Using this facility, several design-basis and performance tests were conducted to validate the passive safety systems of SMART. Among these, three 2-inch small-break loss-of-coolant accident tests were introduced, where the operating conditions of the passive safety injection system (PSIS) and passive residual heat removal system (PRHRS) were different. The main difference between the test results was in the reactor vessel (RV) level. Both PSIS and PRHRS contributed to the RV levels. The tests were also simulated using a system analysis code, MARS-KS. Using the code, major parameters were predicted reasonably well. The physical phenomena behind core makeup tank (CMT) injection were explored in depth by referring to the code calculation results, and the suspension of CMT injection was simulated by considering the heat loss at the CMT wall.
引用
收藏
页数:10
相关论文
共 24 条
[1]  
[Anonymous], 2014, Advances in Small Modular Reactor Technology Developments
[2]  
Bae H., 2013, FESTADD1302
[3]   Core makeup tank injection characteristics during different test scenarios using SMART-ITL facility [J].
Bae, Hwang ;
Ryu, Sung Uk ;
Jeon, Byong-Guk ;
Yang, Jin-Hwa ;
Yun, Eunkoo ;
Bang, Yun-Gon ;
Yi, Sung-Jae ;
Park, Hyun-Sik .
ANNALS OF NUCLEAR ENERGY, 2019, 126 :10-19
[4]   Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design [J].
Bae, Hwang ;
Kim, Dong Eok ;
Ryu, Sung-Uk ;
Yi, Sung-Jae ;
Park, Hyun-Sik .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (05) :968-978
[5]   ASSESSMENT OF CONDENSATION HEAT TRANSFER MODEL TO EVALUATE PERFORMANCE OF THE PASSIVE AUXILIARY FEEDWATER SYSTEM [J].
Cho, Yun-Je ;
Kim, Seok ;
Bae, Byoung-Uhn ;
Park, Yusun ;
Kang, Kyoung-Ho ;
Yun, Byong-Jo .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2013, 45 (06) :759-766
[6]  
Fletcher C. D., 1997, INEL960400
[7]   Simulated AP600 response to small-break loss-of-coolant-accident and non-loss-of-coolant-accident events: Analysis of SPES-2 integral test results [J].
Friend, MT ;
Wright, RF ;
Hundal, R ;
Hochreiter, LE ;
Ogrins, M .
NUCLEAR TECHNOLOGY, 1998, 122 (01) :19-42
[8]  
Ishii M., 1983, NUREGCR3267
[9]   Code validation on a passive safety system test with the SMART-ITL facility [J].
Jeon, Byong Guk ;
Cho, Yeon-Sik ;
Bae, Hwang ;
Kim, Yeon-Sik ;
Ryu, Sung-Uk ;
Suh, Jae-Seung ;
Yi, Sung-Jae ;
Park, Hyun-Sik .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, 54 (03) :322-329
[10]  
KAERI, 2009, KAERI/TR-2812