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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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
Preliminary Evaluation of Rare Earth Effect on Burnup Limit in TRU Fuel
한국방사성폐기물학회 학술대회
2018 .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
사용후핵연료저장조 연소도곡선 불만족 해결방안 연구
한국에너지학회 학술발표회
2018 .04
경수로 연소이력을 반영한 사용후핵연료 선원항 평가
한국에너지학회 학술발표회
2023 .10
고연소도 사용후핵연료봉의 단순화 모델 개발
대한기계학회 춘추학술대회
2022 .05
A Criticality Analysis of the GBC-32 Dry Storage Cask with Hanbit Nuclear Power Plant Unit 3 Fuel Assemblies from the Viewpoint of Burnup Credit
Nuclear Engineering and Technology
2016 .06
Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
Nuclear Engineering and Technology
2018 .01
Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool
Nuclear Engineering and Technology
2023 .06
Compound effects of operating parameters on burnup credit criticality analysis in boiling water reactor spent fuel assemblies
Nuclear Engineering and Technology
2018 .01
연소이력을 반영한 사용후핵연료 붕괴열 계산
한국에너지학회 학술발표회
2018 .04
Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
Nuclear Engineering and Technology
2021 .04
Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
Nuclear Engineering and Technology
2020 .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
Determination of Plutonium and Uranium Content and Burnup Using Six Group Delayed Neutrons
Nuclear Engineering and Technology
2019 .01
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Nuclear Engineering and Technology
2021 .09
중수로 연료 노내 장전위치별 방출 연소도 분포
한국에너지학회 학술발표회
2023 .10
심층처분시스템 설계를 위한 경수로 사용후핵연료 현황 분석
방사성폐기물학회지
2019 .01
Towards inferring reactor operations from high-level waste
Nuclear Engineering and Technology
2024 .07
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