(A) study on the modeling of molten corium-concrete interaction = 노심용융물과 콘크리트 상호작용의 모델링에 대한 연구

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The phenomenon known as molten corium concrete interaction (MCCI) has been recognized as important aspects of severe reactor accidents. The potential hazard of a MCCI is the threat to the integrity of the containment building due to the possibility of a basemat melt through, containment overpressurization by noncondensible gases, or oxidation of combustible gases. Over the past several years, a large experimental and analytical effort has been under taken in corium-concrete interaction phenomena by several organization. The purpose of this paper is to investigate the previous analytical results and computer programs, and finally to establish a new stand alone model which can predict the corium-concrete interaction. A model to predict the behavior of molten corium-concrete interaction in the reactor cavity during vessel ruptured accidents is established. Gas film model, gas bubble model, slag model and periodic contact model are employed as a major heat transfer model between corium and concrete. Solidified debris crust is considered at the boundary of molten corium. Upon the experimental observations, no layer stratification is assumed due to the strong dispersion of the metallic melt in the oxidic phase. With the assumption of temperature profile within the corium pool and crust, the temperature distribution of concrete is found by explicit solution of heat conduction equation. The sideward heat transfer rate can be obtained by considering multiplication factor to the downward heat transfer rate. The multiplication factor is treated as a user input because of its large uncertainty. Comparisons are made with two large scale experiments, SURC-2 and BETA V3.3. There is a reasonable agreement in the corium temperature, erosion depth and gas generation between the experimental data and the predicted results with periodic contact model given the uncertainties in the input data or the measurement. The gas bubble model has the highest heat transfer coefficient, and th...
Advisors
Chang, Soon-Heungresearcher장순흥researcher
Description
한국과학기술원 : 원자력공학과,
Publisher
한국과학기술원
Issue Date
1994
Identifier
69256/325007 / 000911253
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력공학과, 1994.2, [ x, 66 p. ]

URI
http://hdl.handle.net/10203/49298
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=69256&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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