Performanc of triso-coated HTGR fissile fuel particles during in-block carbonization [electronic resource]
This investigation determined the effect of heating rate of the carbonization cycle, fissile particle crushing strength after both silicon carbide coating and outer low-temperature isotropic (OLTI) coating, and horizontal and vertical positions of the fuel within the fuel element block on pitch coke...
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Corporate Author: | |
Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1979.
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Subjects: |
MARC
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245 | 0 | 0 | |a Performanc of triso-coated HTGR fissile fuel particles during in-block carbonization |h [electronic resource] |
260 | |a Oak Ridge, Tenn. : |b Oak Ridge National Laboratory. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1979. | ||
300 | |a Pages: 38 : |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 SciTech Connect. | ||
500 | |a 03/01/1979. | ||
500 | |a "ornl/tm-6779" | ||
500 | |a Caputo, A.J.; Johnson, D.R.; Bayne, C.K. | ||
520 | 3 | |a This investigation determined the effect of heating rate of the carbonization cycle, fissile particle crushing strength after both silicon carbide coating and outer low-temperature isotropic (OLTI) coating, and horizontal and vertical positions of the fuel within the fuel element block on pitch coke yield and defective fraction of fissile fuel particle coatings. A carbonization run at each of four heating rates using three fissile particle batches gave three levels of particle crushing strength. Fuel rods made from each of the three particle batches were placed in one of three vertical positions and in one of three horizontal positions. Following the pitch coke yield determination, half of the sample rods were analyzed for defective SiC coatings and half for defective OLTI coatings. Results verified that in-block carbonization can produce acceptable HTGR fuel rods with respect to pitch coke yield and defective fraction of SiC coatings. The defective fraction of SiC coatings was controlled by the SiC crushing strength. The in-block carbonization process can produce acceptable HTGR fuel rods. 12 figures, 6 tables. | |
536 | |b W-7405-ENG-26. | ||
650 | 7 | |a Coated Fuel Particles. |2 local. | |
650 | 7 | |a Carbonization. |2 local. | |
650 | 7 | |a Failures. |2 local. | |
650 | 7 | |a Fuel Rods. |2 local. | |
650 | 7 | |a Fabrication. |2 local. | |
650 | 7 | |a Coatings. |2 local. | |
650 | 7 | |a Experimental Data. |2 local. | |
650 | 7 | |a Htgr Type Reactors. |2 local. | |
650 | 7 | |a Pyrolytic Carbon. |2 local. | |
650 | 7 | |a Silicon Carbides. |2 local. | |
650 | 7 | |a Tables. |2 local. | |
650 | 7 | |a Thorium Oxides. |2 local. | |
650 | 7 | |a Uranium Carbides. |2 local. | |
650 | 7 | |a Uranium Dioxide. |2 local. | |
650 | 7 | |a Actinide Compounds. |2 local. | |
650 | 7 | |a Carbides. |2 local. | |
650 | 7 | |a Carbon. |2 local. | |
650 | 7 | |a Carbon Compounds. |2 local. | |
650 | 7 | |a Chalcogenides. |2 local. | |
650 | 7 | |a Chemical Reactions. |2 local. | |
650 | 7 | |a Data. |2 local. | |
650 | 7 | |a Data Forms. |2 local. | |
650 | 7 | |a Decomposition. |2 local. | |
650 | 7 | |a Elements. |2 local. | |
650 | 7 | |a Fuel Elements. |2 local. | |
650 | 7 | |a Fuel Particles. |2 local. | |
650 | 7 | |a Gas Cooled Reactors. |2 local. | |
650 | 7 | |a Graphite Moderated Reactors. |2 local. | |
650 | 7 | |a Information. |2 local. | |
650 | 7 | |a Nonmetals. |2 local. | |
650 | 7 | |a Numerical Data. |2 local. | |
650 | 7 | |a Oxides. |2 local. | |
650 | 7 | |a Oxygen Compounds. |2 local. | |
650 | 7 | |a Reactor Components. |2 local. | |
650 | 7 | |a Reactors. |2 local. | |
650 | 7 | |a Silicon Compounds. |2 local. | |
650 | 7 | |a Thorium Compounds. |2 local. | |
650 | 7 | |a Uranium Compounds. |2 local. | |
650 | 7 | |a Uranium Oxides. |2 local. | |
650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
650 | 7 | |a Materials Science. |2 edbsc. | |
710 | 2 | |a Oak Ridge National Laboratory. |4 res. | |
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/6456632 |z Online Access (via OSTI) |
907 | |a .b90536290 |b 03-09-23 |c 02-15-17 | ||
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