Integrated FHR Technology Development Final Report: Tritium Management, Materials Testing, Salt Chemistry Control, Thermal Hydraulics and Neutronics with Associated Benchmarking

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Report Date:  October 2018
Appendices: No

Abstract

This report summarizes the results of a 3-year Integrated Research Project (IRP) sponsored by the U.S. Department of Energy to address major technical challenges in the development of the Fluoride-salt-cooled High-temperature Reactor (FHR). The IRP universities included the Massachusetts Institute of Technology (MIT), the University of California at Berkeley (UCB), the University of Wisconsin (UW), and the University of New Mexico (UNM). The FHR is a new reactor concept less than 20 years old that combines (1) a clean fluoride salt coolant, (2) the graphite-matrix coated-particle fuel originally developed for High-Temperature Gas-Cooled Reactors and (3) passive decay heat removal systems from sodium fast reactors. The base-line design is a pebble-bed FHR that delivers heat between 600 to 700°C with a 7Li2BeF4 (flibe) salt coolant to the power cycle or industrial users...

 
Program:     ANP : Advanced Nuclear Power Program

Type:     TR 

RPT. No.: 180