Uncertainty Analysis of Transportable Fluoride-Salt-Cooled High Temperature Reactor（TFHR）

The uncertainty and sensitivity quantification investigation of MIT proposed 20 MWth prismatic Transportable Fluoride-salt-cooled High Temperature Reactor（TFHR） is performed with the DAKOTA code coupled to the commercial nuclear best-estimate software RELAP5.Model input parameters were selected with specified variations and probability density functions,a total of 200 steady state calculations were then conducted in order to statistically determine 95% peak fuel temperature tolerance intervals with 95% confidence level.It was found that uncertainties in the heat transfer coefficient and helium gap were the most significant contributors to the propagated peak fuel temperature uncertainty.About 0.5% of calculated fuel temperatures exceeded the fuel damage.The current design of THFR needs further optimization from the prospective of thermal-hydraulics.