Molybdenum-base cermet fuel development [electronic resource]
Nesdps Office Of Nuclear Energy Space And Defense Power Systems.
Saved in:
| Online Access: |
Online Access |
|---|---|
| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Richland, Wash. : Oak Ridge, Tenn. :
Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1987.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Molybdenum-base cermet fuel development |h [electronic resource] |
| 260 | |a Richland, Wash. : |b Pacific Northwest National Laboratory (U.S.) ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1987. | ||
| 300 | |a Pages: 7 : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 07/01/1987. | ||
| 500 | |a "pnl-sa-15107" | ||
| 500 | |a " conf-880122-7" | ||
| 500 | |a "DE88005529" | ||
| 500 | |a 5. symposium on space nuclear power systems, Albuquerque, NM, USA, 11 Jan 1988. | ||
| 500 | |a Moss, R.W.; Gurwell, W.E.; White, G.D.; Pilger, J.P. | ||
| 520 | 3 | |a Development of a multimegawatt (MMW) space nuclear power system requires identification and resolution of several technical feasibility issues before selecting one or more promising system concepts. Demonstration of reactor fuel fabrication technology is required for cermet-fueled reactor concepts. MMW reactor fuel development activity at Pacific Northwest Laboratory (PNL) is focused on producing a molybdenum-matrix uranium-nitride (UN) fueled cermet. This cermet is to have a high matrix density (greater than or equal to95%) for high strength and high thermal conductance coupled with a high particle (UN) porosity (approx.25%) for retention of released fission gas at high burnup. Fabrication process development involves the use of porous TiN microspheres as surrogate fuel material until porous UN microspheres become available. Process development has been conducted in the areas of microsphere synthesis, particle sealing/coating, and high-energy-rate forming (HERF) and vacuum hot press consolidation techniques. This paper summarizes the status of these activities. | |
| 520 | 0 | |a Nesdps Office Of Nuclear Energy Space And Defense Power Systems. | |
| 536 | |b AC06-76RL01830. | ||
| 650 | 7 | |a Molybdenum. |2 local. | |
| 650 | 7 | |a Nuclear Fuels. |2 local. | |
| 650 | 7 | |a Microspheres. |2 local. | |
| 650 | 7 | |a Porosity. |2 local. | |
| 650 | 7 | |a Pnictides. |2 local. | |
| 650 | 7 | |a Uranium Compounds. |2 local. | |
| 650 | 7 | |a Space Power Reactors. |2 local. | |
| 650 | 7 | |a Uranium Nitrides. |2 local. | |
| 650 | 7 | |a Transition Element Compounds. |2 local. | |
| 650 | 7 | |a Isotopes. |2 local. | |
| 650 | 7 | |a Power Reactors. |2 local. | |
| 650 | 7 | |a Hot Pressing. |2 local. | |
| 650 | 7 | |a Actinide Compounds. |2 local. | |
| 650 | 7 | |a Fuels. |2 local. | |
| 650 | 7 | |a Feasibility Studies. |2 local. | |
| 650 | 7 | |a Elements. |2 local. | |
| 650 | 7 | |a Nitrides. |2 local. | |
| 650 | 7 | |a Energy Sources. |2 local. | |
| 650 | 7 | |a Cermets. |2 local. | |
| 650 | 7 | |a Materials. |2 local. | |
| 650 | 7 | |a Fabrication. |2 local. | |
| 650 | 7 | |a Reactor Materials. |2 local. | |
| 650 | 7 | |a Metals. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Mobile Reactors. |2 local. | |
| 650 | 7 | |a Sputtering. |2 local. | |
| 650 | 7 | |a Pressing. |2 local. | |
| 650 | 7 | |a Composite Materials. |2 local. | |
| 650 | 7 | |a Titanium Nitrides. |2 local. | |
| 650 | 7 | |a Titanium Compounds. |2 local. | |
| 650 | 7 | |a Nitrogen Compounds. |2 local. | |
| 650 | 7 | |a Transition Elements. |2 local. | |
| 650 | 7 | |a Radioactive Materials. |2 local. | |
| 650 | 7 | |a Fission Products. |2 local. | |
| 650 | 7 | |a Materials Working. |2 local. | |
| 650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Pacific Northwest Laboratory. |4 res. | |
| 710 | 2 | |a Pacific Northwest National Laboratory (U.S.). |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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