DSpace at KOASAS
College of Engineering(공과대학)Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)

NE-Conference Papers(학술회의논문)

Search for

Recent Items

rss_1.0 rss_2.0 atom_1.0

Collection's Items (Sorted by Submit Date in Descending order): 4941 to 4960 of 5611

4941
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

4942
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

4943
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

4944
Fatigue Properties of Inconel 690 Steam Generator Tubing Materials

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

4945
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

4946
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

4947
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

4948
Development of an Integrated Knowledge-Base and its Management Tool for Comupterized Alarm Processing System

장순흥, KNS Spring Meeting, 1997

4949
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

4950
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

4951
Effect of hydride morphology on fracture toughness of Russian pressure tube materials

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

4952
High cycle fatigue properties of Inconel 690

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

4953
Analysis of stress state in the ball indentation test of reactor pressure vessel steel

김인섭, Proceding of the 11-th Conferencs on Mechanical behaviors of Materials, pp.489 - 498, 1997

4954
Development of Performance Meassure for Advanced Alarm System Using Signal Detection Theory

Park, JK; Choi, SS; Chang, Soon-Heung, '96 CSEPC, 1996

4955
Knowledge Base Verification Based on Enhanced Colored Petri Net

Kim, Jong Hyun; Seong, Poong-Hyun, 한국원자력학회 '97 추계학술발표회, pp.271 - 276, 한국원자력학회, 1997-11

4956
Analysis of the Nuclear Subcriticality for the High Density Spent Fuel Storage at PWR Plants

Koh, D.J; Jo. C.K; Ryu, H.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.470 - 475, 1998-05

4957
Evaluation of U-Zr Hydride Fuel for a Thorium Fuel Cycle in an RTR Concept

Lee, K.T; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.52 - 57, 1998-05

4958
Fuel Self-Sufficient and Low Proliferation Risk Multi-Recycling of Spent Fuel

Cho, Nam-Zin; Hong, S.G; Kim, T.H, The 13th KAIF/KNS Annual Conference, pp.417 -, 1998-04

4959
The Use of Burnup Credit in Criticality Control for the Korean Spent Fuel Management Program

Koh, D.J; Jo, C.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997

4960
Stability Analysis of an Accelerator Driven Fluid-Fueled Subcritical Reactor System

Cho, Nam-Zin; Kim, D.S, Proc. of the Korean Nuclear Society Spring Meeting, pp.90 - 95, 1997-05

Discover

rss_1.0 rss_2.0 atom_1.0