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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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Level 1 probabilistic safety assessment of supercritical ? CO 2 ? cooled micro modular reactor in conceptual design phase
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Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
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Technology Selection for Offshore Underwater Small Modular Reactors
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Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
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Limit Load Evaluation of Primary Cooling System for Research Reactor
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PSA를 이용한 연구용 원자로 안전성 향상 방안 도출
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Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
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Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants
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Aspects of Preliminary Probabilistic Safety Assessment for a Research Reactor in the Conceptual Design Phase
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INSTRUMENTATION AND CONTROL STRATEGIES FOR AN INTEGRAL PRESSURIZED WATER REACTOR
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Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
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Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
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A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
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Comparative study on response of thiocyanate shock load on continuous and fed batch anaerobic-anoxic-aerobic sequential moving bed reactors
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Vessel failure sensitivities of an advanced reactor for SBLOCA
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On the cyclic change in the dynamics of the IBR-2M pulsed reactor
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신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
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냉각재상실사고 시 안전주입탱크 유로저항계수가 일체형 원자로에 미치는 영향
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