NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 4541 to 4560 of 5611

4541
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

4542
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

4543
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

4544
Intermediate Probabilistic Safety Assessment Approach for Safety Critical Digital Systems

Kang, Hyun Gook, ICONE9, 2001

4545
A Design Guide of Digital I&C Systems from the Viewpoint of PSA

Kang, Hyun Gook, Core University Program, 2001

4546
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

4547
Evaluation of the Impact of the Digital Safety-Critical I&C Systems on the Plant Risk

Kang, Hyun Gook, ISOFIC 2002, 2002

4548
Probabilistic Safety Assessment on the Fault-Tolerant Mechanism of Digital I&C Systems

Kang, Hyun Gook, 원자력학회 2000춘계학술발표회, 원자력학회, 2000

4549
Digital I&C System in Nuclear Power Plants and Probabilistic Safety Analysis

Kang, Hyun Gook, KINS, 2000

4550
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

4551
An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant

Jang, Changheui, Proc. of PVP2002, 2002-09-30

4552
PSA as a Measure of Digital Systems' safety

Kang, Hyun Gook, 원자력학회 2001 춘계 학술발표회, 원자력학회, 2001

4553
The Effect of Safety and Risk Perception on The Public Acceptance of Nuclear Energy

Kang, Hyun Gook, 원자력학회 2001 추계 학술발표회, 원자력학회, 2001

4554
디지털 원자로보호계통이 원전 안전성에 미치는 영향에 관한 단순화된 정량 분석

강현국; 장승철; 하재주, 한국원자력학회 2002년도 추계학술발표회, pp.85 - 85, 한국원자력학회, 2002-10

4555
PSA 기법을 이용한 원자력 설비의 필수 보호 지역 파악 방법

양준언; 박창규; 최선영; 김재환; 강현국, 한국원자력학회 2002년도 추계학술발표회, pp.199 - 199, 한국원자력학회, 2002-10

4556
Korean Activities in Safety Assessment of Digital Safety System

Kang, Hyun Gook, OECD Halden W/S, 2002

4557
Chemical Impurity Study on the Polyaniline by the positron Annihilation

Cho, Gyuseong, , 1999-08

4558
Seasonal Influence of Countermeasures for Milk After Accident

Cho, Gyuseong, , 1999-10

4559
Scattered Neutron Calibration Field of KAERI

Cho, Gyuseong, , 1999-10

4560
Application of the LIGA Process for Fabrication of Gas Avalanche Devices

Cho, Gyuseong, IEEE NSS & MIC, pp.633 - 637, IEEE NSS & MIC, 2000-10

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