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

被引：12

作者：

Bae, Hwang ^{[1
]}

Kim, Dong Eok ^{[2
]}

Ryu, Sung-Uk ^{[3
]}

Yi, Sung-Jae ^{[3
]}

Park, Hyun-Sik ^{[3
]}

机构：

[1] Korea Atom Energy Res Inst, SMART Reactor Design Div, 111,Daedeok Daero 989 Beon Gil, Daejeon 34057, South Korea

[2] Kyungpook Natl Univ, Dept Precis Mech Engn, 2559 Kyeongsang Daero, Sangju 37224, Kyeongbuk, South Korea

[3] Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, 111,Daedeok Daero 989 Beon Gil, Daejeon 34057, South Korea

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2017年 / 49卷 / 05期

基金：

新加坡国家研究基金会;

关键词：

Small-break loss-of-coolant accident; System-integrated Modular Advanced ReacTor; Thermal-ehydraulic phenomena; Safety injection; Core uncovery; NUCLEAR HEATING REACTOR;

D O I：

10.1016/j.net.2017.04.006

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：

Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermalehydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery. (C) 2017 Korean Nuclear Society, Published by Elsevier Korea LLC.

引用

页码：968 / 978

页数：11

共 23 条

[1]

[Anonymous], 2012, INT ATOMIC ENERGY AG

[2]

[Anonymous], 2005, INT ATOMIC ENERGY AG

[3]

[Anonymous], 2014, INT ATOMIC ENERGY AG

[4]

[Anonymous], 2006, INT ATOMIC ENERGY AG

[5] 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

[6] Considerations for in-service inspection on pressure vessel of 200MW nuclear heating reactor [J].

Chang, HJ ;

He, SY ;

Liu, JJ .

NUCLEAR ENGINEERING AND DESIGN, 2000, 202 (01) :11-16

[7]

CHUNG B. D., 2009, KAERITR37802009

[8]

Ishii M., 1983, Similarity Analysis and Scaling Criteria for LWR's under Single-Phase and Two Phase Natural Circulation

[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]

Kang K.H., 2011, KAERITR43162011

← 1 2 3 →