NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4941 to 4960 of 5619

4941
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

4942
Development of a Scaling Factor Prediction Method for Radionuclide Composition in Low-Level Radioactive Waste

이건재, 한국원자력학회 춘계학술발표회, pp.833 - 838, 1995

4943
Decision Making Using AHP (Analytic Hierachy Process) and Fuzzy Set Theory in Waste Management

Lee, Kun Jai, Proceedings of the 5rd Int'l Conference on Radioactive Waste Management and Environmental Remediation, pp.1113 - 1116, 1995

4944
Adsorption of Cobalt on Bentonite in the Presence of EDTA

Lee, Kun Jai, Proceedings of the 5rd Int'l Conference on Radioactive Waste Management and Environmental Remediation, pp.1109 - 1111, 1995

4945
Development of an Intermediate Level Computer Code for the Atmospheric Dispersion and Dose Assessment

Lee, Kun Jai, Proc. of the 5th Topical Meetings on Emergency Preparedness and Response, pp.438 - 442, 1995

4946
Fuzzy Colored Petri Nets and Their Application to Efficient Design and V&V of Fuzzy Logic Controllers

Son, Han Seong; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.91 - 91, 한국원자력학회, 1998-10

4947
Integrated Knowledge base Tool for Aquistion and Verification of NPP Alarm System

Park, Joo Hyun; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.80 - 80, 한국원자력학회, 1998-10

4948
Experimental Analysis of Specification Language Impact on NPP Software Diversity

Yoo, Chang Sik; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.76 - 76, 한국원자력학회, 1998-10

4949
A Combined Procedure of RSM and LHS for Uncertainty Analyses in Source Term Quantifications Using MAAP3.0B Code

Chun, Moon Hyun, Proc. of the International Topical Meeting on Probabilistic Safety Assessment (PSA'96), pp.325 - 332, 1996

4950
Predition of the Onset of Slug Flow in Nearly Horizontal Air-Water Countercurrent Flow

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, pp.368 - 373, 1997

4951
Average Liquid Level and Pressure Drop for Countercurrent Stratified Two-Phase Flow

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.301 - 306, 1996

4952
Fatigue Properties of Inconel 690 Steam Generator Tubing Materials

김인섭, Conference on Mechanical Behavior of Materials, pp.303 - 312, 1998

4953
Investigation of the Effect of Resistive MHD Modes on Spherical Torus Performance in CDX-U

Ono, M; Stutman, D; Hwang, YS; Choe, Wonho; Menard, J; Jones, T; Lo, E; et al, IAEA International Conference on Plasma Physics and Controlled Nuclear Fusion Research, pp.71 - 81, 1996

4954
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

4955
Experimental Sutdy and Correlation Development of Critical Heat Flux Under Low Pressure and Low Flow condition

Kim, HC; Baek, WP; Kim, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997

4956
Development of an Integrated Knowledge-Base and its Management Tool for Comupterized Alarm Processing System

장순흥, KNS Spring Meeting, 1997

4957
Effect of Specimen Thickness on Near-Threshold fatigue crack Propagation of SA106 Gr.C Nuclear Main Stream Pipe weld joints

Kim, In Sup, TMS fall meeting a part of materials week '97, pp.15 - 17, 1997

4958
Dynamic strain aging in base weld metal of SA106 Gr.CPiping steel

Kim, In Sup, TMS fall meeting, a part of materials week '97, pp.48 - 49, 1997

4959
Effect of hydride morphology on fracture toughness of Russian pressure tube materials

김인섭, Proceeding of the Korean Nuclear Society Automn meeting, pp.100 -, 1997

4960
High cycle fatigue properties of Inconel 690

김인섭, Proceeding of the Korean Nuclear Society Automn meeting, pp.224 -, 1997

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