Irradiation effects on fuels for space reactors [electronic resource].
- Los Alamos, N.M. : Los Alamos National Laboratory, 1984. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 38 : digital, PDF file
- Additional Creators:
- Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- A review of irradiation-induced swelling and gas release experience is presented here for the three principal fuels UO/sub 2/, UC, and UN. The primary advantage of UC and UN over UO/sub 2/ is higher thermal conductivity and attendant lower fuel temperature at equivalent pellet diameter and power density, while UO/sub 2/ offers the distinct benefit of well-known irradiation performance. Irradiation test results indicate that at equivalent burnup, temperature, and porosity conditions, UC experiences higher swelling than UO/sub 2/ or UN. Fission gas swelling becomes important at fuel temperatures above 1320 K for UC, and at somewhat higher temperatures for UO/sub 2/ and UN. Evidence exists that at equivalent fuel temperatures and burnups, high density UO/sub 2/ and UN experience comparable swelling behavior; however, differences in thermal conductivity influence overall irradiation performance. The low conductivity of UO/sub 2/ results in higher thermal gradients which contribute to fuel microcracking and gas release. As a result UO/sub 2/ exhibits higher fractional gas release than UN, at least or burnups up to about 3%.
- Published through SciTech Connect., 01/01/1984., "la-ur-84-2651", " conf-840113-10", "DE84016460", Symposium on space nuclear power systems, Albuquerque, NM, USA, 10 Jan 1984., and Ranken, W.A.; Cronenberg, A.W.
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