Thulium oxide fuel characterization study: Part 1, Materials properties measurements. [Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/; thulium-170]
Description
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 … continued below
Physical Description
Pages: 110
Creation Information
Nelson, C.A.; Anderson, R.W.; Fink, C.R.; Tse, A. & Fretague, W.J. August 1, 1970.
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Sanders Nuclear Corp., Nashua, NH (USA)
Place of Publication: United States
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Description
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.
Physical Description
Pages: 110
Notes
NTIS, PC A06/MF A01; 1.
Subjects
Keywords
- Alloy-Tzm
- Alloys
- Beta Decay Radioisotopes
- Beta-Minus Decay Radioisotopes
- Capsules
- Chalcogenides
- Chromium Alloys
- Cobalt Alloys
- Cobalt Base Alloys
- Compatibility
- Containers
- Direct Energy Converters
- Electron Capture Radioisotopes
- Elements
- Feasibility Studies
- Hastelloy X
- Hastelloys
- Haynes 25 Alloy
- Heat Resistant Materials
- Heat Resisting Alloys
- Heat Sources
- Intermediate Mass Nuclei
- Iron Alloys
- Isotopes
- Materials
- Melting Points
- Metals
- Molybdenum Alloys
- Molybdenum Base Alloys
- Nesdps Office Of Nuclear Energy Space And Defense Power Systems
- Nickel Alloys
- Nuclei
- Odd-Odd Nuclei
- Oxides
- Oxygen Compounds
- Phase Studies
- Physical Properties
- Radioisotope Heat Sources
- Radioisotopes
- Rare Earth Compounds
- Rare Earth Isotopes
- Rare Earth Nuclei
- Shielding
- Tantalum Alloy-T111
- Tantalum Alloys
- Tantalum Base Alloys
- Thermodynamic Properties
- Thermoelectric Generators
- Thulium 170
- Thulium Compounds
- Thulium Isotopes
- Thulium Oxides
- Titanium Alloys
- Transition Elements
- Transition Temperature
- Tungsten
- Tungsten Alloys
- Uses
- Very High Temperature
- Ytterbium Compounds
- Ytterbium Oxides
- Zirconium
- Zirconium Alloys Nesdps Office Of Nuclear Energy Space And Defense Power Systems 070300* -- Isotopic Power Supplies
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- Other: DE87005218
- Report No.: SNC-3693-5
- Office of Scientific & Technical Information Report Number: 6664784
- Archival Resource Key: ark:/67531/metadc1193665
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- August 1, 1970
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Nelson, C.A.; Anderson, R.W.; Fink, C.R.; Tse, A. & Fretague, W.J. Thulium oxide fuel characterization study: Part 1, Materials properties measurements. [Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/; thulium-170], report, August 1, 1970; United States. (https://digital.library.unt.edu/ark:/67531/metadc1193665/: accessed April 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.