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Results 1-10 of 79 (Search time: 0.003 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

Jhung, MJ; Jang, Changheuiresearcher; Kim, SH; Choi, YH; Kim, HJ; Jung, S; Kim, JM; Sohn, GH; Jin, TE; Choi, TS; Kim, JH; Kim, JW; Park, KB, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.19, no.2, pp.634 - 648, 2005-02

2
Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal Shock

Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Chang, Yoon Suk; Xu, Xiangyuan; Kim, Jong Min; Kim, Jong Wook; Jang, Changheuiresearcher, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.12, pp.1131 - 1139, 2010-12

3
Effect of cyclic strain rate on environmental fatigue behaviors of SA508 Gr.1a low alloy steel in 310°C deoxygenated water

Cho, H.; Jang, H.; Kim, B.K.; Kim, I.S.; Jang, Changheuiresearcher, ADVANCED MATERIALS RESEARCH, v.24-25, no.0, pp.1121 - 1124, 2007

4
Microstructure and hydride embrittlement of zirconium model alloys containing niobium and tin

Oh, Seung Jin; Jang, Changheuiresearcher; Kim, Jun Hwan; Jang, Changheuiresearcher, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.528, no.10-11, pp.3771 - 3776, 2011-04

5
Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Jhung, Myung Jo; Choi, Young Hwan; Jang, Changheuiresearcher, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.46, no.3, pp.310 - 315, 2009-03

6
Experience of the integrity assessment of the highly embrittled reactor pressure vessel for the life extension

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

7
IRRADIATION EMBRITTLEMENT OF CLADDING AND HAZ OF RPV STEEL

Lee J.S; Kim I.S; Jang, Changheuiresearcher; Kimura A, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.5, pp.405 - 410, 2006-08

8
The effects of the stainless steel cladding in pressurized thermal shock evaluation

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

9
Structural integrity assessment of reactor pressure vessels during pressurized thermal shock

Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Jung, Sunggyu; Kim, Jong Min; Kim, Ji Ho; Kim, Jong Wook; Jang, Changheuiresearcher; Chang, Yoon Suk; Kang, Ki Sig, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.22, no.8, pp.1451 - 1459, 2008-08

10
Approximation method for the calculation of stress intensity factors for the semi-elliptical surface flaws on thin-walled cylinder

Jang, Changheuiresearcher, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.20, no.3, pp.319 - 328, 2006-03

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