Silicon carbide as an inert-matrix for a thermal reactor fuel

Silicon carbide as an inert-matrix for a thermal reactor fuel

This paper reports progress on work to develop methods of fabricating silicon carbide with cerium, as a substitute for plutonium, to achieve high densities at low sintering temperatures. Densities of 97–99% of TD were achieved at 1943 K for cerium oxide concentrations in the starting powders from 5...

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Bibliographic Details
Published in:Journal of nuclear materials Vol. 274; no. 1; pp. 54 - 60
Main Authors: Verrall, R.A., Vlajic, M.D., Krstic, V.D.
Format: Journal Article Conference Proceeding
Language:English
Published: Amsterdam Elsevier B.V 01-08-1999
Elsevier
Subjects:
Applied sciences
Energy
Exact sciences and technology
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
A03
F07
T08
F01
S04
Coolant
Cerium
Nuclear fuel
High temperature
Specific heat
Additive
Silicon carbide
Simulation
Irradiation
Thermal conductivity
Plutonium
Low temperature
Thermal degradation
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Summary:This paper reports progress on work to develop methods of fabricating silicon carbide with cerium, as a substitute for plutonium, to achieve high densities at low sintering temperatures. Densities of 97–99% of TD were achieved at 1943 K for cerium oxide concentrations in the starting powders from 5 to 20 wt%. Also reported are: specific heat and thermal conductivity measurements of as-fabricated SiC; compatibility of SiC with coolant and Zircaloy-4; and accelerator simulations of in-reactor fission-fragment damage. The thermal conductivity for as-fabricated SiC with additives was 48 W m −1 K −1 at 298 K decreasing to about 18 W m −1 K −1 at 1773 K. Calculations, based on the measured thermal conductivity, show that the inert-matrix fuel could operate at 55 kW m −1 linear power at a centre-line temperature of only 673 K, i.e., only 100 K above coolant temperature, although it is expected that irradiation-induced degradation of thermal conductivity will lead to higher operating temperatures as burnup accumulates. The increase in central temperatures due to a possible decrease in thermal conductivity caused by fast-neutrons are calculated in the text. SiC appears to be a very promising candidate as an inert-matrix fuel for water-cooled reactors.
ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(99)00089-6