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Conference Article: Effect of water vapor on the release of fission gases from UCO in HTGR coated fuel particles.

Myers, B.F. (Oak Ridge National Lab., TN (United States))

Abstract

The release of fission gas from uranium oxycarbide fuel was measured under hydrolyzing conditions during irradiation of fuel compacts in the High Flux Isotope Reactor. Four water vapor injection experiments at partial pressures between 21 and 199 Pa and temperatures between 755 and 779 deg. C were conducted at selected times. Three isotopes of krypton (85mKr, 87Kr, 88Kr) and of xenon (133Xe, 135Xe, 138Xe) were measured. The prehydrolysis fission gas release was found to be dependent on the fission rate density. During and after a water vapor injection experiment, there were typically three distinct responses: (1) an initial, rapid release. (2) a steady release. And (3) a decline in release after termination of injection. The major contribution to the initial release was stored fission gas. The quantity released depended on the square of the partial pressure of water vapor but was independent of the fission gas element or isotope. The iodine precursors of 133Xe and 135Xe contributed significantly to the initial release of the xenon isotopes. The interaction of H2O with the UC2 and UO2 was found to be sequential and was attributed to a slow movement of water vapor into the fuel compact as a result of reaction with the carbonaceous pore walls of the compact matrix material. The release of fission gas from each fuel kernel was rapid (80 s) following carbide hydrolysis but was slow (2 h) during the H2O-UO2 interaction. The steady release, diffusional in nature, was dominant after the initial rapid release and persisted until the water vapor injection was terminated. The ratio of the steady to the prehydrolysis release was dependent on the element, independent of the isotope of the element, and larger after the carbide portion was hydrolyzed. At the termination of water vapor injection, the fission gas release declined as the fuel sintered.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Behaviour of gas cooled reactor fuel under accident conditions. Proceedings of a specialists meeting held in Oak Ridge, 5-8 November 1990
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--25, pp:143-151