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3-D CFD Analysis of the CANDU-6 Moderator Circulation Under Nnormal Operating Conditions
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  • 3-D CFD Analysis of the CANDU-6 Moderator Circulation Under Nnormal Operating Conditions
  • 3-D CFD Analysis of the CANDU-6 Moderator Circulation Under Nnormal Operating Conditions
저자명
Yoon. Churl,Rhee. Bo-Wook,Min. Byung-Joo
간행물명
Journal of the Korean Nuclear Society
권/호정보
2004년|36권 6호|pp.559-570 (12 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

A computational fluid dynamics model for predicting moderator circulation inside the Canada deuterium uranium (CANDU) reactor vessel has been developed to estimate the local subcooling of the moderator in the vicinity of the calandria tubes. The buoyancy effect induced by the internal heating is accounted for by the Boussinesq approximation. The standard $k-{varepsilon}$ turbulence model with logarithmic wall treatment is applied to predict the turbulent jet flows from the inlet nozzles. The matrix of the calandria tubes in the core region is simplified to a porous media in which the anisotropic hydraulic impedance is modeled using an empirical correlation of pressure loss. The governing equations are solved by DFX-4.4, a commercial CFD code developed by AEA technology. The resultant flow patterns of the constant-z slices containing the inlet nozzles and the outlet port are "mined-type", as observed in the former 2-dimensional experimental investigations. With 103% full power for conservatism, the maximum temperature of the moderator is $82.9^{circ}C$ at the top of the core region. Considering the hydrostatic pressure change, the minimum subcooling is $24.8^{circ}C$.