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Results 1-8 of 8 (Search time: 0.004 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Simulant melt experiments on in-vessel retention through external reactor vessel cooling

Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.155, no.3, pp.324 - 339, 2006-09

2
The applicability of a quenching mesh as a hydrogen flame arrester in nuclear power plants

Hong, SW; Song, JH; Kim, HD; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.153, no.1, pp.89 - 99, 2006-01

3
CRITICAL HEAT FLUX ENHANCEMENT

Chang, Soon-Heung; Jeong, Yong Hoon; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11

4
Flow analysis using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling

Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.33, no.11-12, pp.966 - 974, 2006-07

5
Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01

6
Prediction of the human response time with the similarity and quantity of information

Lee, S; Heo, G; Chang, Soon-Heung, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.6, pp.728 - 734, 2006-06

7
Team crystallization (SIO2): Dynamic model of team effectiveness evaluation under the dynamic and tactical environment at nuclear installation

Kim, Sok Chul; Chang, Soon-Heung; Heo, Gyunyoung, SAFETY SCIENCE, v.44, no.8, pp.701 - 721, 2006-10

8
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes

Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02

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