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Showing results 1 to 4 of 4

1
Analytical work of nuclear reactor pressure vessel rupture size enlargement during severe accidents = 중대사고시 원자로 압력 용기 파손 크기 확장에 관한 해석적 연구link

Song, Mun Won; No, Hee Cheon; et al, 한국과학기술원, 2018

2
CFD-assisted analytical work of pressure vessel rupture size enlargement during severe accidents

Song, Mun Won; No, Hee-Cheon, 2018 Iron and Steel Technology Conference and Exposition, pp.1263 - 1264, Association for Iron and Steel Technology, AISTECH, 2018-05

3
Development of a semi -empirical model -based COrium COolability analysis tool (COCOA) validated against a large scale corium experiment, FARO

Kim, Jaeha; Yoon, S. H.; Song, Mun Won; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.364, 2020-08

4
Experimental study and validation of MARS code for CCFL in passive emergency core cooling system (PECCS) of public acceptable simple SMR (PASS) system

Kim, Ho Sik; Song, Mun Won; No, Hee-Cheon, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, pp.1848 - 1857, American Nuclear Society, 2015-08

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