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1
Experience of the integrity assessment of the highly embrittled reactor pressure vessel for the life extension

Hong, SY; Jang, Changheui; Jeong, IS, NUCLEAR ENGINEERING AND DESIGN, v.214, no.1-2, pp.163 - 172, 2002-05

2
Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel

Jeong, IS; Jang, Changheui; Park, JH; Hong, SY; Jin, TE; Yuem, HG; Jeong, SG, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.78, no.2-3, pp.99 - 109, 2001

3
The effect of flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock

Jang, Changheui; Jeong, IS; Hong, SY, NUCLEAR ENGINEERING AND DESIGN, v.197, no.3, pp.249 - 264, 2000-05

4
The effects of the stainless steel cladding in pressurized thermal shock evaluation

Jang, Changheui; Kang, SC; Moonn, HR; Jeong, IS; Kim, TR, NUCLEAR ENGINEERING AND DESIGN, v.226, no.2, pp.127 - 140, 2003-12

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