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Criticality effect according to axial burnup profi les in PWR burnup credit analysis
Nuclear Engineering and Technology
2019 .01
Radiation Shielding Evaluation for Spent Fuel Storage Pool According to Burnup
한국방사성폐기물학회 학술대회
2018 .01
iBEST: A PROGRAM FOR BURNUP HISTORY ESTIMATION OF SPENT FUELS BASED ON ORIGEN-S
Nuclear Engineering and Technology
2015 .01
Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems
Nuclear Engineering and Technology
2021 .01
Spent fuel simulation during dry storage via enhancement of FRAPCON-4.0: Comparison between PWR and SMR and discharge burnup effect
Nuclear Engineering and Technology
2022 .12
Preliminary Evaluation of Rare Earth Effect on Burnup Limit in TRU Fuel
한국방사성폐기물학회 학술대회
2018 .01
A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
Nuclear Engineering and Technology
2016 .06
고연소도 사용후핵연료 건식저장을 위한 캐스크 내부압력 측정사례
한국에너지학회 학술발표회
2020 .11
Compound effects of operating parameters on burnup credit criticality analysis in boiling water reactor spent fuel assemblies
Nuclear Engineering and Technology
2018 .01
고연소도 사용후핵연료봉의 단순화 모델 개발
대한기계학회 춘추학술대회
2022 .05
Modelling of the Spent Nuclear Fuel Assembly Using the Monte Carlo Method
한국방사성폐기물학회 학술대회
2017 .01
Domain Decomposition Strategy for Pin-Wise Full-Core Monte Carlo Depletion Calculation with the Reactor Monte Carlo Code
Nuclear Engineering and Technology
2016 .06
Evaluation of Preliminary Criticality Safety for Metal Storage Cask
한국방사성폐기물학회 학술대회
2018 .01
15 m Drop Analysis for Spent Nuclear Fuel Transport Cask
한국방사성폐기물학회 학술대회
2018 .01
Impact of fuel temperature on nuclear core design calculations
Nuclear Engineering and Technology
2024 .09
CO2 Credit is essential
한국자동차공학회 Workshop
2016 .09
Fixed neutron absorbers for improved nuclear safety and better economics in nuclear fuel storage, transport and disposal
Nuclear Engineering and Technology
2023 .06
중수로 연료 노내 장전위치별 방출 연소도 분포
한국에너지학회 학술발표회
2023 .10
Criticality Analysis for Loading Curve Generation for OASIS-32D Cask With PLUS7 Fuel
한국방사성폐기물학회 학술대회
2018 .01
경수로 사용후핵연료 건식저장용기 간 중성자 표면선속 간섭률 평가
방사선산업학회지
2024 .06
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