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A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
Nuclear Engineering and Technology
2020 .09
Conceptual Designs and Characteristic of the Fuel Handling and Transfer System for 150 MWe PGSFR and 1400 MWe SFR Burner Reactor
Nuclear Engineering and Technology
2022 .11
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor
Nuclear Engineering and Technology
2024 .09
연구로 작업수조 내의 CFD 해석
대한기계학회 춘추학술대회
2017 .11
연료품질 및 연비계산 방법 변화에 따른 연비특성 분석
동력시스템공학회지
2016 .08
탄소중립연료(E-Fuel) 연구개발 현황
한국연소학회지
2022 .03
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
Reactor Internal Core Modelling Methodology for APR1400 under Dynamic Loading Condition
대한기계학회 춘추학술대회
2019 .11
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
Effect of DUPIC Cycle on CANDU Reactor Safety Parameter
Nuclear Engineering and Technology
2016 .01
Method to Determine the Simplified Fuel Assembly Model for a Spent Fuel Rack Seismic Analysis From the Reactor Vessel Internal Seismic Analysis Model
한국방사성폐기물학회 학술대회
2018 .01
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS
Nuclear Engineering and Technology
2015 .04
Fixed neutron absorbers for improved nuclear safety and better economics in nuclear fuel storage, transport and disposal
Nuclear Engineering and Technology
2023 .06
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