4541 | Wire Spacer 형상이 압력강하에 미치는 영향에 관한 실험적 연구 (An Experimental Investigation of Wire Spacer Geometry Effects on Pressure Drop) 전문헌, 한국원자력학회 99 추계학술발표회, 1999 |
4542 | 수직관 벽면을 통한 열유속 측정 및 보정 방법 (A Measurement and Compensation Method of the Heat Flux through a Vertical Tube Wall) 전문헌, 한국원자력학회 99 추계학술발표회, 1999 |
4543 | A Theoretical and Experimental Study of the Steam Condensation Effect on the CCFL in Nearly Horizontal Two-Phase Flow 전문헌, 대한기계학회 1999년도 열공학부문 추계학술대회, pp.515 - 523, 1999 |
4544 | Simple Measure of Uncertainty Importance Using Entire Change of Cumulative Distribution Functions Chun, Moon Hyun, Proc. of the International Topical Meeting on Probabilistic Safety Assessment (PSA99), pp.269 - 278, 1999 |
4545 | Space-Dependent Feedback Kinetics Calculation in the Anayltic Function Expansion Nodal Method Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2000-05 |
4546 | Whole-Core Heterogeneous Transport Calculations and Their Comparison with Diffusion Results Lee, G.S; Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, 2000-05 |
4547 | Acceleration of the Method of Characteristics in the CRX Lattice Calculation Code for Anisotropic Scattering Problems Lee, G.S; Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclar Society Autumn Meeting, pp.49 -, 1999-10 |
4548 | Generation of the Analytic Solutions of the Multigroup Discrete Ordinates Transport Equation in Slab Geometry by Using Infinite Medium Green's Function Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, v.1, pp.47 -, 1999-10 |
4549 | Reactor Physics and Nuclear Engineering Education in Korea Cho, Nam-Zin, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.XIV.A.-7 -, 2000-05 |
4550 | Comparison of Criticality Benchmark Calculations on the UO2 and MOX Fuel Arrays Using ENDF/B-V and ENDF/B-VI Data Ahn, J.G; Cho, Nam-Zin, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.C-1 -, 2000-05 |
4551 | Transition Cycle Behavior of the Pan-Shape Transuranic Burner Core with Low Sodium Void Reactivity Kim, S.J; Cho, Nam-Zin; Kim, Y.J, Eighth International Conference on Nuclear Engineering, 2000-04 |
4552 | Intermediate Probabilistic Safety Assessment Approach for Safety Critical Digital Systems Kang, Hyun Gook, ICONE9, 2001 |
4553 | A Design Guide of Digital I&C Systems from the Viewpoint of PSA Kang, Hyun Gook, Core University Program, 2001 |
4554 | A Comparative Design Analysis of Transuranic Burner Cores with Low Sodium Void Reactivity Kim, S.J; Cho, Nam-Zin; Kim, Y.J, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.C.-1 -, 2000-05 |
4555 | Evaluation of the Impact of the Digital Safety-Critical I&C Systems on the Plant Risk Kang, Hyun Gook, ISOFIC 2002, 2002 |
4556 | Probabilistic Safety Assessment on the Fault-Tolerant Mechanism of Digital I&C Systems Kang, Hyun Gook, 원자력학회 2000춘계학술발표회, 원자력학회, 2000 |
4557 | Digital I&C System in Nuclear Power Plants and Probabilistic Safety Analysis Kang, Hyun Gook, KINS, 2000 |
4558 | Determination of the Initial RTNDT using Master Curve Technology and Implication to RPV Integrity Assessment for Life Extension Jang, Changheui, IAEA specialists Meeting on Master Curve Technology, 2001-09-18 |
4559 | An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant Jang, Changheui, Proc. of PVP2002, 2002-09-30 |
4560 | PSA as a Measure of Digital Systems' safety Kang, Hyun Gook, 원자력학회 2001 춘계 학술발표회, 원자력학회, 2001 |