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
- 2012.1
- 수록면
- 831 - 846 (16page)
이용수
초록· 키워드
오류제보하기
KAERI has developed a two-phase CFD code, CUPID, for a refined calculation of transient two-phase flows related to nuclear reactor thermal hydraulics, and its numerical models have been verified in previous studies. In this paper, the CUPID code is validated against experiments on the downcomer boiling and moderator flow in a Calandria vessel. Physical models relevant to the validation are discussed. Thereafter, multi-scale thermal hydraulic analyses using the CUPID code are introduced. At first, a component-scale calculation for the passive condensate cooling tank (PCCT) of the PASCAL experiment is linked to the CFD-scale calculation for local boiling heat transfer outside the heat exchanger tube. Next, the Rossendorf coolant mixing (ROCOM) test is analyzed by using the CUPID code, which is implicitly coupled with a systemscale code, MARS.
목차
등록된 정보가 없습니다.
참고문헌 (25)
참고문헌 신청
A. Tentner / 2008 / Computational fluid dynamics modeling of two-phase flow topologies in a boiling water reactor fuel assembly / Proc. of ICONE16
A. Tomiyama / 2002 / Transverse migration of single bubbles in simple shear flows / Chemical Engineering Science 57 : 1849 ~ 1858
A.D. Burns / 2004 / The Favre Averaged drag model for turbulence dispersion in Eulerian multiph
B.J. Yun / 2008 / Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400 / Nuclear Engineering and Design 238 : 2064 ~ 2074
C. Frepoli / 2003 / Notes on the implementation of a fully-implicit numerical scheme for a two-phase three-field flow model / Nuclear Engineering and Design 225 : 191 ~ 217
A. Tomiyama / 2002 / Transverse migration of single bubbles in simple shear flows / Chemical Engineering Science 57 : 1849 ~ 1858
A.D. Burns / 2004 / The Favre Averaged drag model for turbulence dispersion in Eulerian multiph
B.J. Yun / 2008 / Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400 / Nuclear Engineering and Design 238 : 2064 ~ 2074
C. Frepoli / 2003 / Notes on the implementation of a fully-implicit numerical scheme for a two-phase three-field flow model / Nuclear Engineering and Design 225 : 191 ~ 217
이 논문의 저자 정보
최근 본 자료
댓글(0)
0