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.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2023.12
- 수록면
- 50 - 56 (7page)
- DOI
- 10.5293/kfma.2023.26.6.050
이용수
이 논문의 연구 히스토리 (2)
- 이 논문의 후속연구가 궁금하신가요?
- 연관 학술논문 또는 학술발표를 통해 보다 발전된 연구결과를 확인하실 수 있습니다.
- 이 논문의 연구 히스토리 확인하기
초록· 키워드
오류제보하기
After several major nuclear accidents, extensive research has been conducted on passive and inherent safety concepts to improve the safety of nuclear reactors for decades. However, research on inherent safety concepts that always maintain the reactivity coefficient of the core as a negative value is somewhat lacking compared to passive safety concepts. Therefore, in this study, thermal-hydraulic analysis of the density lock used in the PIUS-type reactor, which enhances the inherent safety of the reactor and enables operation without control rods, was conducted. The density lock with open ends isolates the primary system from a large borated-water pool using the thermal-hydraulic characteristics, without relying on mechanical devices such as valve components. However, instability occurs at the hot/cold fluids interface inside the density lock and unintentionally affects the core reactivity under normal operation. Therefore, the PIUS-type reactor was simulated using the one-dimensional thermal-hydraulic numerical simulation code, the MARS-KS code. The analysis results showed that stratification instability generates heat losses caused by convection and conduction, and also decreases the core reactivity due to the continuous boron molecule leakage toward the primary side. To ensure stable operation without control rods in the PIUS-type reactor, additional reactivity coefficient control will be required. This study not only emphasizes the inherent safety of nuclear reactors to ensure their reliability and safety but also suggests it as an innovative safety technology for nuclear reactors in the future, contributing to the safe operation of nuclear reactors.
목차
ABSTRACT
1. 서론
2. 해석적 모델
3. 해석 결과
4. 요약 및 향후 계획
References
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
-
시뮬레이션 데이터 생성을 통한 기계학습 기반 원자로 노심 이상 탐지 방법론
대한산업공학회지
2021 .04
-
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
-
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
Nuclear Engineering and Technology
2024 .03
-
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
-
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
-
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
-
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
-
Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)
Nuclear Engineering and Technology
2015 .04
-
Safety Classification of Systems, Structures and Components for Pool Type Research Reactor
Nuclear Engineering and Technology
2016 .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
-
냉각재상실사고 시 안전주입탱크 유로저항계수가 일체형 원자로에 미치는 영향
대한기계학회 춘추학술대회
2020 .12
-
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
-
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
-
An integrated risk-informed safety classification for unique research reactors
Nuclear Engineering and Technology
2023 .05
-
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
-
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
-
Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
-
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
이 논문의 저자 정보
최근 본 자료
댓글(0)
0