NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4541 to 4560 of 5619

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

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