Fabrication and Characterization of Surrogate TRISO Particles Using 800μm ZrO<sub>2</sub> Kernels [electronic resource]
In support of fully ceramic microencapsulated (FCM) fuel development, coating development work is ongoing at Oak Ridge National Laboratory (ORNL) to produce tri-structural isotropic (TRISO) coated fuel particles with both UN kernels and surrogate (uranium-free) kernels. The nitride kernels are used...
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Corporate Author: | |
Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2016.
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Subjects: |
MARC
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245 | 0 | 0 | |a Fabrication and Characterization of Surrogate TRISO Particles Using 800μm ZrO<sub>2</sub> Kernels |h [electronic resource] |
260 | |a Washington, D.C. : |b United States. Office of the Assistant Secretary for Nuclear Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2016. | ||
300 | |a 31 p. : |b digital, PDF file. | ||
336 | |a text |b txt |2 rdacontent. | ||
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500 | |a "ornl/ltr--2016/315" | ||
500 | |a "AF5810000" | ||
500 | |a "NEAF278" | ||
500 | |a Brian C. Jolly; Grant Helmreich; Kevin M. Cooley; John Dyer; Kurt Terrani. | ||
520 | 3 | |a In support of fully ceramic microencapsulated (FCM) fuel development, coating development work is ongoing at Oak Ridge National Laboratory (ORNL) to produce tri-structural isotropic (TRISO) coated fuel particles with both UN kernels and surrogate (uranium-free) kernels. The nitride kernels are used to increase fissile density in these SiC-matrix fuel pellets with details described elsewhere. The surrogate TRISO particles are necessary for separate effects testing and for utilization in the consolidation process development. This report focuses on the fabrication and characterization of surrogate TRISO particles which use 800μm in diameter ZrO<sub>2</sub> microspheres as the kernel. | |
536 | |b AC05-00OR22725. | ||
650 | 7 | |a Accident-Tolerant Nuclear Fuels. |2 local. | |
650 | 7 | |a Zirconium Oxides. |2 local. | |
650 | 7 | |a Silicon Carbides. |2 local. | |
650 | 7 | |a Uranium Nitrides. |2 local. | |
650 | 7 | |a Coated Fuel Particles. |2 local. | |
650 | 7 | |a Fabrication. |2 local. | |
650 | 7 | |a Fuel Pellets. |2 local. | |
650 | 7 | |a Ceramics. |2 local. | |
650 | 7 | |a Matrix Materials. |2 local. | |
650 | 7 | |a Microspheres. |2 local. | |
650 | 7 | |a Testing. |2 local. | |
650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
710 | 2 | |a Oak Ridge National Laboratory. |4 res. | |
710 | 1 | |a United States. |b Office of the Assistant Secretary for Nuclear Energy. |4 spn. | |
710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
856 | 4 | 0 | |u http://www.osti.gov/scitech/biblio/1325475 |z Online Access (via OSTI) |
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