Fluoride-Salt-Cooled High-Temperature Reactor (FHR) with Silicon-Carbide-Matrix Coated-Particle Fuel

Conference · Sun Jan 01 00:00:00 EST 2012

OSTI ID:1047644

Forsberg, C. W. ^[1]; Terrani, Kurt A ^[2]; Snead, Lance Lewis ^[2]; Katoh, Yutai ^[2]

---

1. Massachusetts Institute of Technology (MIT)
2. ORNL

The FHR is a new reactor concept that uses coated-particle fuel and a low-pressure liquid-salt coolant. Its neutronics are similar to a high-temperature gas-cooled reactor (HTGR). The power density is 5 to 10 times higher because of the superior cooling properties of liquids versus gases. The leading candidate coolant salt is a mixture of {sup 7}LiF and BeF{sub 2} (FLiBe) possessing a boiling point above 1300 C and the figure of merit {rho}C{sub p} (volumetric heat capacity) for the salt slightly superior to water. Studies are underway to define a near-term base-line concept while understanding longer-term options. Near-term options use graphite-matrix coated-particle fuel where the graphite is both a structural component and the primary neutron moderator. It is the same basic fuel used in HTGRs. The fuel can take several geometric forms with a pebble bed being the leading contender. Recent work on silicon-carbide-matrix (SiCm) coated-particle fuel may create a second longer-term fuel option. SiCm coated-particle fuels are currently being investigated for use in light-water reactors. The replacement of the graphite matrix with a SiCm creates a new family of fuels. The first motivation behind the effort is to take advantage of the superior radiation resistance of SiC compared to graphite in order to provide a stable matrix for hosting coated fuel particles. The second motivation is a much more rugged fuel under accident, repository, and other conditions.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1047644
• Resource Relation: Conference: American Nuclear Society Winter Meeting, San Diego, CA, USA, 20121111, 20121115
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BOILING POINTS
COATED FUEL PARTICLES
COOLANTS
FLIBE
FUEL CANS
GAS COOLED REACTORS
GASES
GRAPHITE
MIXTURES
NEUTRONS
PERFORMANCE
POWER DENSITY
RADIATIONS
SPECIFIC HEAT
WATER