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High-temperature fuel technology for nuclear process heat: ZrC-containing coated particle fuels and high-density graphite fuel matrices

Technical Report ·
DOI:https://doi.org/10.2172/5361609· OSTI ID:5361609

This is the final report on the high-temperature, gas-cooled reactor fuels project that was pursued at the Los Alamos Scientific Laboratory from early 1973 to mid-1977. This work followed two broad paths: (1) ZrC was utilized in various ways to improve the temperature capability of fission-product-retaining coated nuclear fuel particles and (2) techniques were developed for fabricating fuel rods by extruding the coated particles in high-density graphite matrices. The key to the ZrC coating project proved to be the ZrCl/sub 4/ powder feeder development. The ZrCl/sub 4/ reacted with H/sub 2/ and CH/sub 4/ or C/sub 3/H/sub 6/ to produce chemically vapor-deposited (CVD) ZrC. This CVD ZrC was used on nuclear fuel particles for replacing the SiC in the TRISO-II design, for making ZrC-C graded coats, and for making ZrC-alloyed isotropic carbon coats. Fuel particles with all of the described coats have been very successful in high-temperature, full-fluence (8 x 10/sup 21/ n cm/sup -2/) irradiation tests. High-temperature diffusion experiments with cesium showed that ZrC is comparable to SiC as a diffusion barrier. Extruded fuel rods with matrix densities of 1.6 to 1.7 g cm/sup -3/ and with up to 45-vol percent coated particles were made without difficulty. All fuel rods tested in high-temperature, full-fluence irradiations had excellent results.

Research Organization:
Los Alamos Scientific Lab., N.Mex. (USA)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
5361609
Report Number(s):
LA-6984
Country of Publication:
United States
Language:
English