NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4961 to 4980 of 5619

4961
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

4962
Development of Performance Meassure for Advanced Alarm System Using Signal Detection Theory

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

4963
Knowledge Base Verification Based on Enhanced Colored Petri Net

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

4964
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

4965
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

4966
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

4967
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

4968
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

4969
An Efficient Multigrid Algorithm for the Reactor Eigenvalue Problems

Cho, Nam-Zin; Lee, K.H; Kim, Y.H, Proc. of the Korean Nuclear Society Spring Meeting, pp.27 - 32, 1997-05

4970
Design Analysis of a Thorium Fueled Reactor with Seed-Blanket Assembly Configuration

Cho, Nam-Zin; Lee, K.T, Proc. of the Korean Nuclear Society Spring Meeting, pp.21 - 26, 1997-05

4971
FN-Based Nodal Transport Method in X-Y Geometry

Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.39 - 44, 1996-11

4972
Boundary Element Method for the Homogenization of the Baffle/Reflector

Cho, Nam-Zin; Cheng, H.W; Park, C.J, Proc. of the Korean Nuclear Society Autumn Meeting, pp.27 - 32, 1996-11

4973
Delayed Hopfield-like Neural Network for Solving Inverse Radiation Transport Problems

Lee, S.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.21 - 26, 1996-11

4974
Image Reconstruction in Emission Computed Tomography via Multigrid Wavelet-Based Natural Pixel Method

Park, C.J; Cho, Nam-Zin, International Conference on the Physics of Nuclear Science and Technology, pp.1703 -, 1998-10

4975
Feasibility Study of Constant Composition TRU Feeding in an Accelerator-Driven Fluid-Fueled Thermal Reactor System

Kim, D.S; Cho, Nam-Zin; Park, W.S, International Conference on the Physics of Nuclear Science and Technology, pp.1563 -, 1998-10

4976
Multi-Recycleing of Spent Fuel with Low Proliferation Risk

Greenspan, E; Cho, Nam-Zin; Hong, S.G; Kim, T.H; Kastenberg, W.E., International Conference on Emerging Nuclear Energy System, 1998-06

4977
Wavelet-Based Image Reconstruction in Transmission Computed Tomography

Cho, Nam-Zin; Park, C.J; Park, J.W, ANS Radiation Protection and Shielding Division Topical Conference, pp.141 -, 1998-04

4978
A Hofield-Like Neural Network with Random Updating Intervals for Solving Inverse Radiation Transport Problems

Lee, S.H; Cho, Nam-Zin, Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications, pp.1245 -, 1997-10

4979
Stability Analysis of An Accelerator-Deiven Subcritical Fluid-Fueled Reactor System for Radioactive Waste Transmutation

Kim, D.S; Cho, Nam-Zin, Internation Conference on Future Nuclar Systejms, v.2, pp.1393 -, 1997-10

4980
Thermal Hydraulic Design Parameters Study for Severe Accidents Using Neural Network

Roh, CH; Chang, KS; Chang, Soon-Heung, The 6th International Conference on Nuclear Engineering, 1998

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