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Results 1-10 of 58 (Search time: 0.008 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Effect of dynamic strain aging on the low cycle fatigue behavior of ASME SA508 CL.3 steel for nuclear pressure vessels

Kim, In Sup; Lee Byung-Ho, Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19), v.287, pp.87 - 91, 1994-06-19

2
Dynamic Strain-Aging Effect on Fracture Toughness of Steel

Kim, In Sup, American Nuclear Society, pp.251 - 253, 1990

3
Effect of Heat Treatment on Microstructure and Mechanical Properties of 12%Cr Steel, Hangzou, China

Kim, In Sup, 1st Pacific Rim International Conference on Advanced Materials and Processing, pp.23 - 27, 1992

4
Role of Compressive Stess on Initial Deformation During Small Punch Test, Transactions of American Nuclear Society, Vol.71, 192-193, 1994

Kim, In Sup, American Nuclear Society, pp.192 - 193, 1994

5
Dynamic Strain Ageing Effect on Fracture Toughness of Vessel Steels, IAEA Technical Committee Meeting, 14-17 May 1991,

Kim, In Sup, IAEA Technical Committee Meeting and Workshop, pp.14 - 17, 1991

6
Positron Annihilation Technique for the Detection of Defects in High Purity Titanium

Kim, In Sup, in Proc. of the Second Pacific Rim International Conference on Advanced Materials and Processing(PRICM-2), Advanced Materials and Pforcessing, ed. by K.S Shin, J.K. Yoon and S.J. Kim, The Korean Institute of Metals and Materials, pp.1159 - 1164, 1995

7
Mechanical Properties of SA106 Gr.C Piping Steel

Kim, In Sup, International Forgemasters Meeting, pp.151 - 162, 1997

8
Investigation of Initial Deformation Behavior during Small Punch Test

Kim, In Sup, in Proc. of the Second Pacific Rim International Conference on Advanced Materials and Processing(PRICM-2), Advanced Materials and Pforcessing, ed. by K.S Shin, J.K. Yoon and S.J. Kim, The Korean Institute of Metals and Materials, pp.1235 - 1240, 1995

9
Effect of dynamic strain aging on fracture toughness for main steam line piping of nuclear power plant

Kim, In Sup, Proceedings of the Workshop on the integrity of Nuclear Component, pp.2 - 2, 1997

10
Annealing of Neutron-Irradiated Linde 80 Reactor Pressure Vessel(RPV) Steel Weld

Kim, In Sup, Plant Life Extension, 1992

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