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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
SAFETY ASPECTS OF INTERMEDIATE HEAT TRANSPORT AND DECAY HEAT REMOVAL SYSTEMS OF SODIUM-COOLED FAST REACTORS
Nuclear Engineering and Technology
2015 .04
금속연료 소듐냉각고속로 중대사고 고유안전특성 SAS4A/SASSYS-1 코드 전산해석
한국전산유체공학회지
2021 .03
소듐냉각고속로 잔열제거계통의 나선형 소듐-공기 열교환기 해석을 위한 1차원 시스템 코드 모델링 및 해석
대한기계학회 춘추학술대회
2024 .11
Thermal Analysis for Spent Nuclear Fuel Temporary Storage System in Pyroprocessing Facility
한국방사성폐기물학회 학술대회
2017 .01
Preliminary design of a production automation framework for a pyroprocessing facility
Nuclear Engineering and Technology
2018 .01
열전달 증진을 위한 SFR 핵연료 집합체 적용 새로운 패턴의 와이어 스페이서
한국유체기계학회 학술대회 논문집
2015 .12
Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)
한국방사성폐기물학회 학술대회
2017 .01
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
Chemical Process Safety at a Pyroprocess Facility
한국방사성폐기물학회 학술대회
2017 .01
An Integrated Multicriteria Decision-Making Approach for Evaluating Nuclear Fuel Cycle Systems for Long-term Sustainability on the Basis of an Equilibrium Model: Technique for Order of Preference by Similarity to Ideal Solution, Preference Ranking Organization Method for Enrichment Evaluation, and Multiattribute Utility Theory Combined with Analytic Hierarchy Process
Nuclear Engineering and Technology
2017 .01
A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS
Nuclear Engineering and Technology
2015 .04
Design and dynamic simulation of a molten salt THS coupled to SFR
Nuclear Engineering and Technology
2024 .04
IDENTIFICATION OF SAFETY CONTROLS FOR ENGINEERING-SCALE PYROPROCESS FACILITY
Nuclear Engineering and Technology
2015 .01
소듐냉각고속로 원형로 중간열전달계통 고온배관의 파단전누설 예비평가
한국압력기기공학회 논문집
2016 .06
Use of similarity indexes to identify spatial correlations of sodium void reactivity coefficients
Nuclear Engineering and Technology
2020 .11
Density of Molten Salt Mixtures of Eutectic LiCl-KCl Containing UCl<sub>3</sub>, CeCl<sub>3</sub>, or LaCl<sub>3</sub>
방사성폐기물학회지
2017 .01
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
Review on sodium corrosion evolution of nuclear-grade 316 stainless steel for sodium-cooled fast reactor applications
Nuclear Engineering and Technology
2021 .11
Methodologies and Properties of Safety Analyses for Pyroprocessing Facilities
한국방사성폐기물학회 학술대회
2018 .01
On the Particle Swarm Optimization of Cask Shielding Design for a prototype Sodium-cooled Fast Reactor
Nuclear Engineering and Technology
2019 .01
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