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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Demonstration of an ultrasonic imaging system for molten lead
Nuclear Engineering and Technology
2024 .04
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor
Nuclear Engineering and Technology
2020 .01
초음파 습식 자기분류법을 이용한 MgxNiyZn1-x-yFe2O4 나노입자 제조
한국표면공학회지
2017 .06
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior
Nuclear Engineering and Technology
2024 .06
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
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
스테인리스강 표면의 젖음 특성 에이징 효과
한국정밀공학회 학술발표대회 논문집
2015 .05
Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model
Nuclear Engineering and Technology
2024 .04
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
Comparative study on response of thiocyanate shock load on continuous and fed batch anaerobic-anoxic-aerobic sequential moving bed reactors
Environmental Engineering Research
2015 .03
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
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