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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
DYNAMIC MODELING AND ANALYSIS OF ALTERNATIVE FUEL CYCLE SCENARIOS IN KOREA
Nuclear Engineering and Technology
2007 .01
A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM
Nuclear Engineering and Technology
2007 .01
FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS
Nuclear Engineering and Technology
2012 .01
Fabrication of Metal Fuel Rodlets for Sodium-cooled Fast Reactor
대한용접학회 특별강연 및 학술발표대회 개요집
2012 .05
TECHNICAL RATIONALE FOR METAL FUEL IN FAST REACTORS
Nuclear Engineering and Technology
2007 .01
금속연료를 사용하는 소듐냉각 고속로의 안전특성
에너지공학
2014 .12
FAST REACTOR TECHNOLOGY R&D ACTIVITIES IN CHINA
Nuclear Engineering and Technology
2007 .01
ELECTROCHEMICAL PROCESSING OF USED NUCLEAR FUEL
Nuclear Engineering and Technology
2011 .01
Development and Validation of a Nuclear Fuel Cycle Analysis Tool: A Future Code
Nuclear Engineering and Technology
2013 .01
Dynamic Modeling of the Korean Nuclear Euel Cycle
한국방사성폐기물학회 학술대회
2004 .01
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit
Nuclear Engineering and Technology
2016 .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
소듐 고속로 연료집합체 내부의 열유동 수치해석
한국유체기계학회 학술대회 논문집
2017 .12
Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)
한국방사성폐기물학회 학술대회
2017 .01
FRENCH PROGRAM TOWARDS AN INNOVATIVE SODIUM COOLED FAST REACTOR
Nuclear Engineering and Technology
2007 .01
Impact of Multi-dimensional Core Thermal-hydraulics on Inherent Safety of Sodium-Cooled Fast Reactor
대한기계학회 춘추학술대회
2008 .11
Sensitivity Analysis of Fabrication Parameters for Dry Process Fuel Performance Using Monte Carlo Simulations
Nuclear Engineering and Technology
2004 .01
The Investigation of Burnup Characteristics Using the Serpent Monte Carlo Code for a Sodium Cooled Fast Reactor
Nuclear Engineering and Technology
2014 .01
Seismic modeling and analysis for sodium-cooled fast reactor
Structural engineering and mechanics : An international journal
2012 .01
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