Thermal hydraulics analysis of the Advanced High Temperature Reactor

• Published in: Nuclear engineering and design 2015-12, Vol.294 (C), p.73-85
• Main Authors: Wang, Dean, Yoder, Graydon L., Pointer, David W., Holcomb, David E.
• Format: Article
• Language: English
• Subjects: GENERAL STUDIES OF NUCLEAR REACTORS
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2015.08.017

•The TRACE AHTR model was developed and used to define and size the DRACS and the PHX.•A LOFF transient was simulated to evaluate the reactor performance during the transient.•Some recommendations for modifying FHR reactor system component designs are discussed. The Advanced High Temperature Reactor (AHTR) is a liquid salt-cooled nuclear reactor design concept, featuring low-pressure molten fluoride salt coolant, a carbon composite fuel form with embedded coated particle fuel, passively triggered negative reactivity insertion mechanisms, and fully passive decay heat rejection. This paper describes an AHTR system model developed using the Nuclear Regulatory Commission (NRC) thermal hydraulic transient code TRAC/RELAP Advanced Computational Engine (TRACE). The TRACE model includes all of the primary components: the core, downcomer, hot legs, cold legs, pumps, direct reactor auxiliary cooling system (DRACS), the primary heat exchangers (PHXs), etc. The TRACE model was used to help define and size systems such as the DRACS and the PHX. A loss of flow transient was also simulated to evaluate the performance of the reactor during an anticipated transient event. Some initial recommendations for modifying system component designs are also discussed. The TRACE model will be used as the basis for developing more detailed designs and ultimately will be used to perform transient safety analysis for the reactor.