NSE - Nuclear Science & Engineering at MIT


Fluoride-salt-cooled high-temperature reactor (FHR)

The FHR is an advanced reactor that combines high-temperature reactor fuel developed for gas cooled reactors with a liquid salt coolant. This combination gives the FHR the capability to couple to a Nuclear Air-Brayton Combined Cycle (NACC) power system similar to power conversion systems used in natural gas plants. NACC enables efficient production of base-load electricity, electric grid stabilization, and the production of peak electricity with use of auxiliary natural gas or ultimately hydrogen. These capabilities may (1) increase plant revenue by up to 50% relative to base-load nuclear power plants and (2) match the needs for a 2030 low-carbon nuclear-electrical grid. MIT leads a consortium including the University of California at Berkeley, the University of Wisconsin, and Westinghouse that is developing this advanced reactor concept.


  1. Forsberg, C. W., et.al. 2013. Fluoride Salt Cooled High-Temperature Reactors (FHRs) for Base Load and Peak Electricity, Grid Stabilization, and Process Heat,” MIT-ANP-TR-147, Massachusetts Institute of Technology Center for Advanced Nuclear Energy Systems, Cambridge, MA, USA (2013), download pdf
  2. Forsberg, C.W., Meeting the Needs of the 2030 Electrical Grid with a Fluoride-Salt-Cooled High-Temperature Reactor (FHR), [Defines FHR Strategy for a commercial machine], March 2013.

Department of Nuclear Science & Engineering

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