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
- 2019.1
- 수록면
- 54 - 59 (6page)
이용수
초록· 키워드
오류제보하기
The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe conditionwith enough safety margins during normal operation and anticipated operational occurrences. In thisresearch, core flow bypass is studied under the conditions of the unavailability of safety systems. As corebypass occurs, the core flow rate is assumed to decrease exponentially with a time constant of 25 s tonew steady state values of 20, 40, 60, and 80% of the nominal core flow rate. The thermal hydraulic codePARET is used through these calculations. Reactor thermal hydraulic stability is reported for all cases ofcore flow bypass.
목차
등록된 정보가 없습니다.
참고문헌 (9)
참고문헌 신청
C. Housiadas / 2000 / Simulation of loss-of-flow transients in research reactors / Ann. Nucl. Energy 27(18):1683~1693
F. Muhammad / 2010 / Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels / Ann. Nucl. Energy 37(4):582~591
H. Kazeminejad / 2008 / Thermal-hydraulic modeling of flow inversion in a research reactor / Ann. Nucl. Energy 35(10):1813~1819
S. E. -D. El-Morshedy / 2011 / Prediction, analysis and solution of the flow inversion phenomenon in a typical MTR-reactor with upward core cooling / Nucl. Eng. Des 241(1):226~235
S. E. -D. El-Morshedy / 2012 / Thermal-hydraulic modeling and analysis of a tank in pool reactor for normal operation and loss of flow transient / Prog. Nucl. Energy 61:78~87
F. Muhammad / 2010 / Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels / Ann. Nucl. Energy 37(4):582~591
H. Kazeminejad / 2008 / Thermal-hydraulic modeling of flow inversion in a research reactor / Ann. Nucl. Energy 35(10):1813~1819
S. E. -D. El-Morshedy / 2011 / Prediction, analysis and solution of the flow inversion phenomenon in a typical MTR-reactor with upward core cooling / Nucl. Eng. Des 241(1):226~235
S. E. -D. El-Morshedy / 2012 / Thermal-hydraulic modeling and analysis of a tank in pool reactor for normal operation and loss of flow transient / Prog. Nucl. Energy 61:78~87
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup
Nuclear Engineering and Technology
2024 .09
-
Predicting the core thermal hydraulic parameters with a gated recurrent unit model based on the soft attention mechanism
Nuclear Engineering and Technology
2024 .06
-
Power upgrading of WWR-S research reactor using plate-type fuel elements part I: Steady-state thermal-hydraulic analysis (forced convection cooling mode)
Nuclear Engineering and Technology
2020 .01
-
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
-
무제어봉 원자로의 고유안전 개념을 지니는 Density Lock 내부 열성층화 불안정성에 대한 고찰
한국유체기계학회 논문집
2023 .12
-
개방수조형 연구용 원자로의 열출력 불확실도 평가
대한기계학회 춘추학술대회
2017 .11
-
Hydraulic performance and flow resistance tests of various hydraulic parts for optimal design of a reactor coolant pump for a small modular reactor
Nuclear Engineering and Technology
2023 .03
-
Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
Nuclear Engineering and Technology
2022 .01
-
터널 굴착기 유압시스템용 유량 제어 블록 개발
한국기계기술학회지
2018 .01
-
유체에 잠겨있는 구조물의 안전성평가 해석
한국기계기술학회지
2015 .01
-
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
-
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
-
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
-
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology
2021 .01
-
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
-
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
-
Performance Characteristics and Flow Field of Axial Flow Hydraulic Turbine in Shallow Open Channel
International Journal of Fluid Machinery and Systems
2018 .12
-
A Study of Enhancing Seismic Resilience of Reactor Internals through Normal Contact between CSB and RV Outlet Nozzle
대한기계학회 춘추학술대회
2024 .11
-
Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code
Nuclear Engineering and Technology
2020 .12
-
Bypass기법을 이용한 G-Pipe가속화
한국정보과학회 학술발표논문집
2022 .12
이 논문의 저자 정보
최근 본 자료
댓글(0)
0