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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM
Nuclear Engineering and Technology
2007 .01
Design of Instrumentation and Control System for Research Reactors
제어로봇시스템학회 국제학술대회 논문집
2011 .10
The Progress of Fast Reactor Technology Development in China
한국방사성폐기물학회 Workshop
2004 .01
FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS
Nuclear Engineering and Technology
2012 .01
ADVANCED SFR DESIGN CONCEPTS AND R&D ACTIVITIES
Nuclear Engineering and Technology
2009 .01
Dynamic Analyse of the Dry Process Fuel Sodium-Coded Fast Reactor Cycle
한국방사성폐기물학회 학술대회
2004 .01
FRENCH PROGRAM TOWARDS AN INNOVATIVE SODIUM COOLED FAST REACTOR
Nuclear Engineering and Technology
2007 .01
LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS
Nuclear Engineering and Technology
2011 .01
Seismic modeling and analysis for sodium-cooled fast reactor
Structural engineering and mechanics : An international journal
2012 .01
소듐냉각고속로 KALIMER-600의 물모의 가시화 실험
대한기계학회 춘추학술대회
2009 .11
CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600
Nuclear Engineering and Technology
2007 .01
Three-dimensional Core Design of a Super Fast Reactor with a High Power Density
Nuclear Engineering and Technology
2010 .01
Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)
한국방사성폐기물학회 학술대회
2017 .01
금속연료를 사용하는 소듐냉각 고속로의 안전특성
에너지공학
2014 .12
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor
Nuclear Engineering and Technology
2020 .01
5㎿ 연구용 원자로의 1차 냉각 계통 유동 특성
한국유체기계학회 논문집
2010 .10
Remote NDT for Inspection of Reactor Vessel Components of Fast Breeder Test Reactor
비파괴검사학회지
2003 .10
Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident
Nuclear Engineering and Technology
2020 .01
소듐냉각 실증로 공기열교환기의 고온 설계 및 손상평가
대한기계학회 춘추학술대회
2012 .05
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