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자료 필터
자료유형
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2011 ~ 2026
2011 2026
키워드
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전체 71건 중 51번부터 60번까지의 결과를 표시합니다.
2021
Article
Evaluation of Depletion Uncertainty for Spent Fuel Storage Pool using Monte Carlo Random Sampling by Considering Boron Concentration in Depletion Calculation
- Choi, Kyu Jung ;
- Kim, Dong Jing ;
- Shin, Chang Ho ;
- Kim, Kiyoung ;
- Hong, Ser Gi
- 2021-10
- 한국원자력학회 추계학술대회 논문집
- 한국원자력학회
Article
A Characterization Study of Nuclear Reactors Through Xenon Isotopic Activity Ratios
- Kim, Sang Woo ;
- Park, Geon Hee ;
- Cho, Yu Yeon ;
- Hong, Ser Gi
- 2021-10
- 한국원자력학회 추계학술대회 논문집
- 한국원자력학회
Article
Recent Advances in STRAUM (SN Transport for Radiation Analysis with Unstructured Meshes) Code
- Woo, MyeongHyeon ;
- Hong, Ser Gi
- 2021-10
- Transactions of the Korean Nuclear Society Virtual Autumn Meeting 2021
- 한국원자력학회
Article
A shutdown dose rates analysis of the Korean fusion demonstration reactor using MCNP5 mesh-based R2S approach
- Kim, Jae Hyun ;
- Woo, Myeong Hyeon ;
- Shin, Chang Ho ;
- Hong, Ser Gi
- 2021-06
- Fusion Engineering and Design
- ELSEVIER SCIENCE SA
Article
Comparison of SCALE 6.1 Monaco/MAVRIC and MCNP calculation for HI-STAR 63
- Kim, Dong Jin ;
- Park, Geon Hee ;
- Cho, Ye seul ;
- Hong, Ser Gi ;
- Gob, Ara ;
- 외 1명
- 2021-05
- 한국원자력학회 춘계학술대회 논문집
- 한국원자력학회
Article
Transition cycle analysis of light water-cooled SMR core loaded with MOX (TRU) and FCM (TRU) fueled PWR assemblies
- Hwang,Dae Hee ;
- Hong, Ser Gi
- 2021-04
- Nuclear Engineering and Design
- ELSEVIER SCIENCE SA
Article
Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems
- Ta, Duy Long ;
- Hong, Ser Gi ;
- Lee, Deokjung
- 2021-01
- Nuclear Engineering and Technology
- KOREAN NUCLEAR SOC
2020
Article
Neutronic analysis of the moderator effect for an ultra long cycle SMSFR (Small Modular Sodium-cooled Fast Reactor)
- Cho, Yu Yeon ;
- Hong, Ser Gi
- 2020-12
- 한국원자력학회 2020 추계학술대회 논문집
- 한국원자력학회
Article
Update of AMORES programs for automatic criticality safety evaluation of the transport cask
- Park,Geon Hee ;
- Kim, Dong Jin ;
- Hong, Ser Gi ;
- Ara Gob ;
- Yook, Dae Sik
- 2020-12
- 한국원자력학회 2020 추계학술대회 논문집
- 한국원자력학회
Article
Development of multi-group cross section processing program for MUST unstructured discrete ordinate transport code
- Woo, Myeong Hyeon ;
- Long, TaDuy ;
- Hong, Ser Gi
- 2020-12
- 한국원자력학회 2020 추계학술대회 논문집
- 한국원자력학회