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|a (TOE)ost7213301
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|a (TOE)7213301
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|a TOE
|c TOE
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|a GDWR
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|a 11
|2 edbsc
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|a 21
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|a E 1.99:ga-a-14320
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|a E 1.99:ga-a-14320
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|a ga-a-14320
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|a Reprocessing yields and material throughput
|h [electronic resource] :
|b HTGR recycle demonstration facility.
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|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1977.
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|a Pages: 109 :
|b digital, PDF file.
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|a text
|b txt
|2 rdacontent.
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|a computer
|b c
|2 rdamedia.
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through SciTech Connect.
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|a 08/01/1977.
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|a "ga-a-14320"
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|a Abraham, L.; Holder, N.
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|a General Atomic Co., San Diego, Calif. (USA)
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|a Recovery and reuse of residual U-235 and bred U-233 from the HTGR thorium-uranium fuel cycle will contribute significantly to HTGR fuel cycle economics and to uranium resource conservation. The Thorium Utilization National Program Plan for HTGR Fuel Recycle Development includes the demonstration, on a production scale, of reprocessing and refabrication processes in an HTGR Recycle Demonstration Facility (HRDF). This report addresses process yields and material throughput that may be typically expected in the reprocessing of highly enriched uranium fuels in the HRDF. Material flows will serve as guidance in conceptual design of the reprocessing portion of the HRDF. In addition, uranium loss projections, particle breakage limits, and decontamination factor requirements are identified to serve as guidance to the HTGR fuel reprocessing development program. (28 tables, 18 figs.)
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|b EY-76-C-03-0167-053.
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|a Fuel Reprocessing Plants.
|2 local.
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|a Performance.
|2 local.
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|a Htgr Type Reactors.
|2 local.
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|a Fuel Cycle.
|2 local.
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|a Demonstration Plants.
|2 local.
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|a Purex Process.
|2 local.
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|a Spent Fuel Elements.
|2 local.
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|a Thorex Process.
|2 local.
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|a Thorium.
|2 local.
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|a Uranium 233.
|2 local.
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|a Actinide Isotopes.
|2 local.
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|a Actinide Nuclei.
|2 local.
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|a Actinides.
|2 local.
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|a Alpha Decay Radioisotopes.
|2 local.
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|a Elements.
|2 local.
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|a Fuel Elements.
|2 local.
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|a Gas Cooled Reactors.
|2 local.
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|a Graphite Moderated Reactors.
|2 local.
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|a Heavy Nuclei.
|2 local.
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|a Isotopes.
|2 local.
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|a Metals.
|2 local.
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|a Nuclear Facilities.
|2 local.
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|a Nuclei.
|2 local.
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|a Radioisotopes.
|2 local.
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7 |
|a Reactors.
|2 local.
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|a Reprocessing.
|2 local.
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|a Even-Odd Nuclei.
|2 local.
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|a Separation Processes.
|2 local.
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|a Reactor Components.
|2 local.
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|a Uranium Isotopes.
|2 local.
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|a Years Living Radioisotopes.
|2 local.
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650 |
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|a Nuclear Fuel Cycle And Fuel Materials.
|2 edbsc.
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650 |
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|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
700 |
1 |
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|a Abraham, L.
|4 aut.
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1 |
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|a Holder, N.
|4 aut.
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2 |
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|a General Atomic Co., San Diego, Calif. (USA)
|4 res.
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1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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|u http://www.osti.gov/servlets/purl/7213301/
|z Online Access
|
907 |
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|a .b7223068x
|b 03-07-23
|c 11-08-12
|
998 |
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|a web
|b 08-04-15
|c f
|d m
|e p
|f eng
|g
|h 0
|i 2
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956 |
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|a Information bridge
|
999 |
f |
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|i 22ef0f6e-82bd-5388-9af9-a733a521b7a7
|s c441c82a-1c4b-51bc-a2aa-99bbe0259b2b
|
952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ga-a-14320
|h Superintendent of Documents classification
|i web
|n 1
|