Integral behavior of the ATLAS facility for a 3-inch small break loss of coolant accident

被引:19
作者
Choi, Ki-Yong [1 ]
Park, Hyun-Sik [1 ]
Cho, Seok [1 ]
Euh, Dong-Jin [1 ]
Kim, Yeon-Sik [1 ]
Baek, Won-Pil [1 ]
机构
[1] Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
关键词
APR1400; ATLAS; SBLOCA; thermal-hydraulics;
D O I
10.5516/NET.2008.40.3.199
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
A small-break loss of coolant accident (SB-LOCA) test with a break size equivalent to a 3-inch cold leg break of the APR1400 was carried out as the first transient integral effect test using the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation). This was the first integral effect test to investigate the integral performance of the test facility and to verify its simulation capability for one of the design-basis accidents. Reasonably good thermal hydraulic data was obtained so that an integral performance of the fluid sub-systems was identified and control performance of the ATLAS was confirmed under real thermal hydraulic conditions. Based on the measured data, a post-test calculation was carried out using the best-estimate thermal hydraulic safety analysis code, MARS 3.1, and the similarity between the expected and actual data was investigated. On the whole, the post-test calculation reasonably predicts the major thermal hydraulic parameters measured during the SB-LOCA test. The obtained data will be used to enhance the simulation capability of the ATLAS and to improve an input model of the ATLAS for simulation of other target scenarios.
引用
收藏
页码:199 / 212
页数:14
相关论文
共 14 条
[1]  
BAE BU, 2007, ICAPP 07 NIC FRANC M
[2]   KAERI integral effect test program and the atlas design [J].
Baek, WP ;
Song, CH ;
Yun, BJ ;
Kwon, TS ;
Moon, SK ;
Lee, SJ .
NUCLEAR TECHNOLOGY, 2005, 152 (02) :183-195
[3]   Simulation capability of the atlas facility for major design-basis accidents [J].
Choi, Ki Yong ;
Park, Hyun Sik ;
Euh, Dong Jin ;
Kwon, Tae Soon ;
Baek, Won Pil .
NUCLEAR TECHNOLOGY, 2006, 156 (03) :256-269
[4]  
CHOI KY, 2007, KAERITR33382007
[5]   Development of passive flow controlling safety injection tank for APR1400 [J].
Chu, In-Cheol ;
Song, Chul-Hwa ;
Cho, Bong Hyun ;
Park, Jong Kyun .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (01) :200-206
[6]  
*INEL, 1998, NUREGCR5535
[7]  
ISHII M, 1983, NUREGCR3267 ANL8332
[8]  
Kim Y.S., 2007, KAERITR33302007
[9]   Integral loop test and assessment of modified RELAP5/MOD3.3 for RCS coolant inventory during a LBLOCA [J].
Kim, Yong-Soo ;
Bae, Byoung-Uhn ;
Park, Goon-Cherl .
NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (02) :182-198
[10]  
MOON SK, 1998, KAERIAR50998