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http://dx.doi.org/10.5855/ENERGY.2012.21.4.419

Preliminary Analysis of the CANDU Moderator Thermal-Hydraulics using the CUPID Code  

Park, Sang Gi (School of Mechanical Engineering, Pusan National University)
Lee, Jae Ryong (Korea Atomic Energy Research Institute(KAERI))
Yoon, Han Young (Korea Atomic Energy Research Institute(KAERI))
Kim, Hyoung Tae (Korea Atomic Energy Research Institute(KAERI))
Jeong, Jae Jun (Korea Atomic Energy Research Institute(KAERI))
Publication Information
Journal of Energy Engineering / v.21, no.4, 2012 , pp. 419-426 More about this Journal
Abstract
A transient, three-dimensional, two-phase flow analysis code, CUPID, has been developed in KAERI. In this work, we performed a preliminary analysis using the CUPID code to investigate the thermal-hydraulic behavior of the moderator in the Calandria vessel of a CANDU reactor. At first, we validated the CUPID code using the three experiments that were performed at Stern Laboratories Inc. To avoid the complexity to generate computational mesh around the Calandria tube bundles, a porous media approach was applied for the region. The pressure drop in the porous media zone was modeled by an empirical correlation. The results of the calculations showed that the CUPID code can predict the mixed flow pattern of forced and natural convection inside the Calandria vessel very well. Thereafter, the analysis was extended to a two-phase flow condition. Also, the local maximum temperature in the Calandria vessel was plotted as a function of the injection flow rate, which may be utilized to predict the local subcooling margin.
Keywords
CANDU; moderator; temperature distribution; two phase flow; CUPID;
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Times Cited By KSCI : 2  (Citation Analysis)
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