Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

被引:1
作者
Kim, Sang Ho [1 ,2 ]
Ham, Jaehyun [1 ]
Lee, Byeonghee [1 ]
Kim, Sung Il [1 ]
Kim, Hwan Yeol [1 ]
Park, Rae-Joon [1 ]
Jung, Jaehoon [1 ]
机构
[1] Korea Atom Energy Res Inst, Daedeok daero 989Beon gil 111, Daejeon 34057, South Korea
[2] Korea Energy Res Inst, Intelligent Accid Mitigat Res Div, Daedeok daero 989Beon gil 111, Daejeon 34057, South Korea
关键词
Severe accident; Molten core; Corium; SMART; MELCOR; MELTSPREAD; MCCI;
D O I
10.1016/j.net.2022.07.030
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 aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions is simulated by the MELCOR code to obtain the conditions for an analysis of the spreading behavior and coolability of the ex-vessel melt. Second, the spreading behavior and coolability of the ex-vessel melt are analyzed by the MELTSPREAD code. The level, temperature, and pressure of the water in the cavity as well as the temperature, mass, composition, and discharge velocity of the melt were utilized to construct the ex-vessel analysis. The melt spread only to part of the cavity, and that the height of the corium in a static state was less than 25 cm. The characteristics of a small modular reactor on the spreading behavior and coolability of melt were analyzed. In the SMART, the amount of melt discharged into the cavity is relatively small and the area of the cavity is sufficiently large when compared to a high-power pressurized water reactor. It was found that the coolability of an exvessel core melt can be sufficiently secured.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:4551 / 4559
页数:9
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