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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
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Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
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2022 .12
Conceptual design of a MW heat pipe reactor
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2024 .03
Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)
Nuclear Engineering and Technology
2015 .04
Evaluation of various large-scale energy storage technologies for fl exible operation of existing pressurized water reactors
Nuclear Engineering and Technology
2021 .08
Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
Power upgrading of WWR-S research reactor using plate-type fuel elements part I: Steady-state thermal-hydraulic analysis (forced convection cooling mode)
Nuclear Engineering and Technology
2020 .01
Design and dynamic simulation of a molten salt THS coupled to SFR
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2024 .04
산업배열 및 부산물을 활용한 1톤급 바이오수소 생산 시뮬레이터 동적 열설계
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2017 .05
Effect of critical flow model in MARS-KS code on uncertainty quantifi cation of large break Loss of coolant accident (LBLOCA)
Nuclear Engineering and Technology
2020 .01
Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors
Nuclear Engineering and Technology
2020 .08
3 MWth 급 매체순환연소 시스템의 운전변수 변화에 따른 성능 예측
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초고온 열저장 시스템에 관한 분석
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Impact of fuel temperature on nuclear core design calculations
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태양광열 기반 하이브리드 히트펌프 시스템의 수치모델링 및 유량별 성능해석
대한설비공학회 학술발표대회논문집
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초고온헬륨루프 및 고온가스로 열유체시험
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Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
동시 축ㆍ방열 조건에서 PCM의 열전달 특성에 관한 연구
설비공학논문집
2016 .08
다중열원 신재생 에너지를 적용한 스마트 빌리지 운영 연구
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