Nuclear Engineering ETDs
Publication Date
Spring 5-16-2026
Abstract
Generation IV reactors, such as the Fluoride salt-cooled High-temperature Reactor (FHR), feature efficient heat transfer and passive heat removal systems. However, accurately predicting thermal behavior under steady-state and transient conditions remains challenging. This work designs and evaluates a twisted tube heat exchanger (TTHX) serving as an intermediate heat exchanger (IHX) and a reactor cavity cooling system (RCCS) serving as a passive decay heat removal system for a generic FHR (gFHR), integrating both systems into a system-level MELCOR model. The TTHX was first designed and assessed using a MATLAB-based framework, followed by detailed MELCOR simulations. The results demonstrate effective heat transfer from the primary FLiBe salt to the secondary side during startup and steady-state operation. Following reactor shutdown, the RCCS removes decay heat through buoyancy-driven natural circulation. Overall, both TTHX and RCCS demonstrate reliable heat transfer performance and support safe operation of a gFHR under steady-state conditions.
Keywords
MELCOR, MATLAB, TTHX, RCCS, FHR
Document Type
Thesis
Language
English
Degree Name
Nuclear Engineering
Level of Degree
Masters
Department Name
Nuclear Engineering
First Committee Member (Chair)
Dr. Minghui Chen
Second Committee Member
Dr. Cassiano R.E. de Oliveira
Third Committee Member
Dr. David Luxat
Recommended Citation
Nguyen, Bao Hoang. "DESIGN AND ANALYSIS OF AN INTERMEDIATE HEAT EXCHANGER AND PASSIVE DECAY HEAT REMOVAL SYSTEM FOR A GENERIC FLUORIDE SALT-COOLED HIGH-TEMPERATURE REACTOR APPLICATION." (2026). https://digitalrepository.unm.edu/ne_etds/155