Development of the FHR advanced natural circulation analysis code and application to FHR safety analysis. (August 2016)

• Record Type: Journal Article
• Authors: Guo, Z.; Zweibaum, N.; Shao, M.; Huddar, L.R.; Peterson, P.F.; Qiu, S.
• Is Part Of: Progress in nuclear energy. Volume 91(2016:Aug.)
• Page Start: 56
• Page End: 67
• Publication Date: 2016-08
• Subjects: FHR -- Natural circulation -- Code methodology; FHR Fluoride-salt-cooled, high-temperature reactor -- CV control volume -- DHX DRACS heat exchanger -- DRACS Direct reactor auxiliary cooling system -- CTAH Coiled tube air heater -- TCHX Thermosyphon-cooled heat exchanger (in DRACS) -- NACC Nuclear air-Brayton combined cycle; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2016.03.022
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: The University of California, Berkeley (UCB) is performing thermal hydraulics safety analysis to develop the technical basis for design and licensing of fluoride-salt-cooled, high-temperature reactors (FHRs). FHR designs investigated by UCB use natural circulation for emergency, passive decay heat removal when normal decay heat removal systems fail. The FHR advanced natural circulation analysis (FANCY) code has been developed for assessment of passive decay heat removal capability and safety analysis of these innovative system designs. The FANCY code uses a one-dimensional, semi-implicit scheme to solve for pressure-linked mass, momentum and energy conservation equations. Graph theory is used to automatically generate a staggered mesh for complicated pipe network systems. Heat structure models have been implemented for three types of boundary conditions (Dirichlet, Neumann and Robin boundary conditions). Heat structures can be composed of several layers of different materials, and are used for simulation of heat structure temperature distribution and heat transfer rate. Control models are used to simulate sequences of events or trips of safety systems. A proportional-integral controller is also used to automatically make thermal hydraulic systems reach desired steady state conditions. A point kinetics model is used to model reactor kinetics behavior with temperature reactivity feedback. The underlying large sparse linear systems in these models are efficiently solved by using direct and iterative solvers provided by the SuperLU code on high performance machines. Input interfaces are designed to increase the flexibility of simulation for complicated thermal hydraulic systems. This paper mainly focuses on the methodology used to develop the FANCY code, and safety analysis of the Mark 1 pebble-bed FHR under development at UCB is performed. Highlights: FHR advanced natural circulation analysis (FANCY) code has been developed. Detailed description of code methodology is done. Safety analysis of Mk1 PB-FHR by FANCY code is performed. The passive mechanisms in the design of the Mk1 PB-FHR guarantee reactor safety.