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
- 2020.1
- 수록면
- 1,386 - 1,395 (10page)
이용수
초록· 키워드
오류제보하기
High fidelity nuclear reactor fuel assembly simulation using CFD method is an effective way for the structure design and optimization. The validated models and user practice guidelines play critical roles in achieving reliable results in CFD simulations. In this paper, the international benchmark MATiS-H is studied carefully and the best user practice guideline is achieved for the rod bundles simulation. Then a 5 5 rod bundles model in the advanced pressurized water reactor (PWR) is established and the detailed three-dimensional thermal-hydraulic characteristics are investigated. The influence of spacer grids and mixing vanes on the flow and hear transfer in rod bundles is revealed. As the coolant flows through the spacer grids and mixing vanes in the rod bundles, the drastic lateral flow would be induced and the pressure drop increases significantly. In addition, the heat transfer is enhanced remarkably due to the strong mixing effects. The calculation results could provide meaningful guidelines for the design of advanced PWR fuel assembly
목차
등록된 정보가 없습니다.
참고문헌 (26)
참고문헌 신청
M. Hassan / 1981 / Heat transfer near spacer grids in gas-cooled rod bundles / Nucl. Technol 52(3):401~414
Y. F. Shen / 1991 / An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle / Nucl. Eng. Des 125(2):111~119
Sun Kyu Yang / 1996 / Moon Ki Chung, Spacer grid effects on turbulent flow in rod bundles / Journal of the Korean Nuclear Society 28
Diana Caraghiaur / 2009 / Experimental investigation of turbulent flow through spacer grids in fuel rod bundles / Nucl. Eng. Des 239:2013~2021
H. L. McClusky / 2003 / Mapping of the lateral flow field in typical subchannels of a support grid with vanes / Journal of Fluids Egineering 125(6):987~996
Y. F. Shen / 1991 / An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle / Nucl. Eng. Des 125(2):111~119
Sun Kyu Yang / 1996 / Moon Ki Chung, Spacer grid effects on turbulent flow in rod bundles / Journal of the Korean Nuclear Society 28
Diana Caraghiaur / 2009 / Experimental investigation of turbulent flow through spacer grids in fuel rod bundles / Nucl. Eng. Des 239:2013~2021
H. L. McClusky / 2003 / Mapping of the lateral flow field in typical subchannels of a support grid with vanes / Journal of Fluids Egineering 125(6):987~996
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Validation of RANS models and Large Eddy simulation for predicting crossfl ow induced by mixing vanes in rod bundle
Nuclear Engineering and Technology
2021 .11
-
Numerical simulation and experimental study of quasi-periodic large-scale vortex structures in rod bundle lattices
Nuclear Engineering and Technology
2024 .02
-
CFD simulation on steam-water two-phase boiling in vertical rod bundle
대한기계학회 춘추학술대회
2019 .04
-
부분 막힘 봉다발 내 유동 분포와 압력 강하 특성에 대한 수치적 연구
대한기계학회 춘추학술대회
2018 .12
-
Modified mixing coeffi cient for the crossfl ow between sub-channels in a 5 × 5 rod bundle geometry
Nuclear Engineering and Technology
2020 .11
-
봉다발 유동에서 혼합날개 지지격자에 의한 단상 대류열전달 향상에 대한 연구
대한기계학회 춘추학술대회
2016 .04
-
전산유체역학 소프트웨어 적용성에 관한 규제 지침 개발을 위한 분할 형태 혼합날개가 장착된 연료집합체 내부유동 분포 수치해석
설비공학논문집
2017 .10
-
혼합날개가 부착된 6×6 봉다발 부수로에서의 열전달 향상을 위한 실험적 연구
한국기계기술학회지
2015 .01
-
가압경수로 핵연료집합체의 유동혼합과 열전달 실험 및 수치 해석
기술과 교육
2021 .09
-
Design and analysis of RIF scheme to improve the CFD effi ciency of rod-type PWR core
Nuclear Engineering and Technology
2021 .10
-
혼합날개를 이용한 6×6 봉다발 부수로에서의 열전달 향상 특성에 관한 실험적 연구
한국기계기술학회지
2017 .01
-
선회 형태 혼합날개가 장착된 연료집합체 내부유동 분포 수치해석
설비공학논문집
2016 .05
-
원자로 봉다발 유동에 대한 RANS 해석 타당성 검토
한국유체기계학회 학술대회 논문집
2020 .08
-
혼합날개 형상이 연료집합체 내부유동 형태에 미치는 영향에 관한 연구
대한기계학회 춘추학술대회
2015 .11
-
비틀림 혼합날개 지지격자의 대류열전달 성능 측정
대한기계학회 춘추학술대회
2015 .11
-
Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method
Nuclear Engineering and Technology
2020 .09
-
Applicability research of round tube CHF mechanistic model in rod bundle channel
Nuclear Engineering and Technology
2021 .02
-
PIV 측정을 통한 난류 구조와 핵료봉 다발의 직교류 혼합사이의 관계에 대한 연구
대한기계학회 춘추학술대회
2015 .11
-
Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles
Nuclear Engineering and Technology
2022 .05
-
Numerical investigation of flow characteristics through simple support grids in a 1 x 3 rod bundle
Nuclear Engineering and Technology
2019 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0