Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Production of LEU Fully Ceramic Microencapsulated Fuel for Irradiation Testing

Conference ·
OSTI ID:1328307

Fully Ceramic Microencapsulated (FCM) fuel consists of tristructural isotropic (TRISO) fuel particles embedded inside a SiC matrix. This fuel inherently possesses multiple barriers to fission product release, namely the various coating layers in the TRISO fuel particle as well as the dense SiC matrix that hosts these particles. This coupled with the excellent oxidation resistance of the SiC matrix and the SiC coating layer in the TRISO particle designate this concept as an accident tolerant fuel (ATF). The FCM fuel takes advantage of uranium nitride kernels instead of oxide or oxide-carbide kernels used in high temperature gas reactors to enhance heavy metal loading in the highly moderated LWRs. Production of these kernels with appropriate density, coating layer development to produce UN TRISO particles, and consolidation of these particles inside a SiC matrix have been codified thanks to significant R&D supported by US DOE Fuel Cycle R&D program. Also, surrogate FCM pellets (pellets with zirconia instead of uranium-bearing kernels) have been neutron irradiated and the stability of the matrix and coating layer under LWR irradiation conditions have been established. Currently the focus is on production of LEU (7.3% U-235 enrichment) FCM pellets to be utilized for irradiation testing. The irradiation is planned at INL s Advanced Test Reactor (ATR). This is a critical step in development of this fuel concept to establish the ability of this fuel to retain fission products under prototypical irradiation conditions.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
NE USDOE - Office of Nuclear Energy
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1328307
Country of Publication:
United States
Language:
English

Similar Records

Fabrication and Irradiation Test Plan for Fully Ceramic Microencapsulated Fuels
Technical Report · Thu Jan 24 23:00:00 EST 2019 · OSTI ID:1564227

Fabrication of UN microsphere kernels for Fully Ceramic Microencapsulated fuel
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:22992096

Production of LEU fully ceramic microencapsulated fuel for irradiation testing
Conference · Fri Jul 01 00:00:00 EDT 2016 · OSTI ID:22765234

Related Subjects