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Showing results 1 to 4 of 4

1
A combined deterministic and probabilistic procedure for safety assessment of beyond design basis accidents in nuclear power plant: Application to ECCS performance assessment for design basis LOCA redefinition

Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.260, pp.165 - 174, 2013-07

2
Assessment of APR-1400 emergency core cooling system performance for design basis LOCA redefinition

Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon Heung; Huh, Byung-Gil; Bang, Young-Seok; Seul, Kwang-Won, 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, American Society of Mechanical Engineers (ASME), 2014-07

3
Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification

Kang, Dong Gu; Jhung, Myung Jo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.241, no.1, pp.257 - 269, 2011-01

4
The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure

Kang, Dong Gu; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.275, pp.142 - 153, 2014-08

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