RELEASE OF FISSION PRODUCTS BY THE IN-PILE BURNING OF IRRADIATED URANIUM CARBIDE-GRAPHITE FUEL
Technical Report
·
OSTI ID:4678065
Three in-pile experiments were conducted to study the behavior of fission products when a fuel of pyrolytic carbon-coated uranium carbide particles in a graphite matrix is exposed to conditions simulating a reactor accident in which air passes over the hot fuel. The fuel was irradiated in a lie stream in the Oak Ridge Research Reactor for 200 hr at 890 deg C and then exposed to air for 15 min at 890 deg C. Combustion commenced, the temperature went up to 1400 deg C, and approximates 0% of the fuel burned in the period of 15 min. The release of Sr, Zr, Ba, and Ce from the furnace was very low, but large fractions of I, Te, Cs, and Ru were released. (D.L.C.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-17-034478
- OSTI ID:
- 4678065
- Report Number(s):
- CONF-39-60
- Country of Publication:
- United States
- Language:
- English
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