An assessment of a LBLOCA similarity for a reduced-height integral effect test loop design for PWRs

被引:12
作者
Park, Hyun-Sik [1 ]
Euh, Dong-Jin [1 ]
Choi, Ki-Yong [1 ]
Kwon, Tae-Soon [1 ]
Baek, Won-Pil [1 ]
机构
[1] Korea Atom Energy Res Inst, Thermal Hydraulics Safety Res Ctr, Taejon 305600, South Korea
关键词
D O I
10.1016/j.anucene.2007.04.004
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 simulation capability of a reduced-height integral effect test loop design has been assessed for a large-break loss-of-coolant accident (LBLOCA) transient in a pressurized water reactor (PWR). A 1/2-height, 1/100-area-scaled model is evaluated against a prototype APR1400 plant by using the best-estimated code, MARS, and the same control logics and accident scenarios. The scaled model and APR1400 are found to have similar thermal-hydraulic responses for the analyzed LBLOCA scenario. It can be concluded from the results of this study that the ATLAS (advanced thermal-hydraulic test loop for accident simulation), which was designed based on the same scaling criteria and now under construction by KAERL can maintain a similarity with the reference APR1400 plant. (c) 2007 Elsevier Ltd. All rights reserved.
引用
收藏
页码:931 / 937
页数:7
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