1980•University of North Texas Digital Library (University of North Texas)Open access
COBRA-WC model and predictions for a fast-reactor natural-circulation transient. [LMFBR]
T.L. George, K.L. Basehore, W.A. Prather
Open full text 0 citations
Abstract
The COBRA-WC (Whole Core) code has been used to predict the core-wide coolant and rod temperature distribution in a liquid metal fast reactor during the early part (first 220 seconds) of a natural circulation transient. Approximately one-sixth of the core was modeled including bypass flows and the pressure losses above and below the core region. Detailed temperature and flow distributions were obtained for the two test fuel assemblies. The COBRA-WC model, the approach, and predictions of core-wide transient coolant and rod temperatures during a natural circulation transient are presented in this paper.
Open-access reader