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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
- 1,231 - 1,240 (10page)
이용수
초록· 키워드
오류제보하기
Unlike land-based nuclear power plants, a marine or floating reactor is affected by external forces due toocean conditions. These external forces can cause additional accelerations and affect each system andequipment of the marine reactor. Therefore, in designing a marine reactor and evaluating its performanceand stability, a thermal hydraulic safety analysis code is necessary to consider the thermal hydrodynamiceffects of ship motion. MARS, which is a reactor system analysis code, includes a dynamicmotion model that can simulate the thermal-hydraulic phenomena under three-dimensional motion bycalculating the body force term included in the momentum equation. In this study, it was verified thatthe dynamic motion model can simulate fluid motion with reasonable accuracy using conceptualproblems. In addition, two modifications were made to the dynamic motion model; first, a user-suppliedtable to simulate a realistic ship motion was implemented, and second, the flow regime map determinationalgorithm was improved by calculating the volume inclination information at every time step ifthe dynamic motion model was activated. With these modifications, MARS could simulate the thermalhydraulicphenomena under ocean motion more realistically
목차
등록된 정보가 없습니다.
참고문헌 (17)
참고문헌 신청
T. Ishida / 1992 / Development of Analysis Code for Thermal Hydrodynamics of Marine Reactor under Multi-Dimensional Ship Motions
J.H. Kim / 1996 / Development of RETRAN-03 Code for Thermal-Hydraulic Analysis of Nuclear Reactor under Multi-Dimensional Motions
J. H. Kim / 2001 / Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions / Nucl. Eng. Des 207:21~31
G. L. Mesina / 2016 / Modeling moving systems with RELAP5-3D / Nucl. Sci. Eng 182:83~95
B. H. Yan / 2011 / The development and validation of a thermal hydraulic code in rolling motion / Ann. Nucl. Energy 38:1728~1736
J.H. Kim / 1996 / Development of RETRAN-03 Code for Thermal-Hydraulic Analysis of Nuclear Reactor under Multi-Dimensional Motions
J. H. Kim / 2001 / Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions / Nucl. Eng. Des 207:21~31
G. L. Mesina / 2016 / Modeling moving systems with RELAP5-3D / Nucl. Sci. Eng 182:83~95
B. H. Yan / 2011 / The development and validation of a thermal hydraulic code in rolling motion / Ann. Nucl. Energy 38:1728~1736
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