지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Development of a Ranging Inspection Technique in a Sodium-cooled Fast Reactor Using a Plate-type Ultrasonic Waveguide Sensor
한국소음진동공학회논문집
2015 .01
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
PGSFR 가동중검사기술 개발
한국압력기기공학회 논문집
2016 .06
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
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verifi cation of Computational Codes
Nuclear Engineering and Technology
2016 .01
PGSFR 소듐냉각고속로 원자로용기 설계 및 구조건전성 평가
한국압력기기공학회 논문집
2016 .06
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
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
소듐냉각고속로 상부내부구조물 열스트라이핑 거동 수치해석 연구
한국전산유체공학회지
2019 .06
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
PGSFR-RVCS 축소모델 평가
대한기계학회 춘추학술대회
2018 .12
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Achieving wetting in molten lead for ultrasonic applications
Nuclear Engineering and Technology
2024 .02
Evaluation for a Sodium Water Reaction Event due to Steam Generator Tubes Break in the PGSFR
Nuclear Engineering and Technology
2016 .01
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
연구용 원자로 격자판에서의 온도분포 평가
대한기계학회 춘추학술대회
2017 .11
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
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
0