Thulium oxide fuel characterization study [electronic resource] : Part 1, Materials properties measurements. [Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/; thulium-170].
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1970.
- Physical Description:
- Pages: 110 : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Scientific and Technical Information
- A feasibility study was performed on encapsulated thulium-170 as an isotopic fuel for operation at temperatures to 1500/sup 0/C for 180 days. Effects of various combinations of fueled capsule design parameters were evaluated and compard to experimental data. A computer program was developed to predict dose rates through various thicknesses of aluminum, stainless steel, lead, tungsten and depleted uranium absorbers using thermoluminescent dosimetry techniques for experimental corroboration. A procedure for preparing Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ composites was evaluated. Melting points and solid-state transformations to the melting point of a composition series 100% Tm/sub 2/O/sub 3/ - 100% Yb/sub 2/O/sub 3/ were determined. The Tm/sub 2/O/sub 3/ - 100% Yb/sub 2/O/sub 3/ system remains cubic to the melting point. Solid-state reaction of candidate containment materials (Hastelloy X, Hastelloy C-276, Haynes-25, T-111, TZM, tungsten and zirconium) with Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ were studied. Containment for times to 10,000 hours at 1600/sup 0/C and to 500 hours at 2000/sup 0/C were demonstrated.
- Published through SciTech Connect., 08/01/1970., "snc-3693-5", "DE87005218", Anderson, R.W.; Fink, C.R.; Fretague, W.J.; Nelson, C.A.; Tse, A., and Sanders Nuclear Corp., Nashua, NH (USA)
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