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|a (TOE)ost5942586
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|a (TOE)5942586
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|a TOE
|c TOE
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|a GDWR
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|a 12
|2 edbsc
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|a 11
|2 edbsc
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| 086 |
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|a E 1.99:pnl-4488
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|a E 1.99:pnl-4488
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| 088 |
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|a pnl-4488
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| 245 |
0 |
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|a Thermal release of volatile fission products from irradiated nuclear fuel
|h [electronic resource]
|
| 260 |
|
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|a Richland, Wash. :
|b Pacific Northwest Laboratory ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1983.
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| 300 |
|
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|a Pages: 74 :
|b digital, PDF file.
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| 336 |
|
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|a text
|b txt
|2 rdacontent.
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| 337 |
|
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through SciTech Connect.
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| 500 |
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|a 06/01/1983.
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| 500 |
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|a "pnl-4488"
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| 500 |
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|a "DE83014906"
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| 500 |
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|a Burger, L.L.; Bray, L.A.; Morgan, L.G.; Baldwin, D.L.
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| 520 |
3 |
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|a An effective procedure for removing /sup 3/H, Xe and Kr from irradiated fuels was demonstrated using Shippingport UO/sub 2/ fuel. The release characteristics of /sup 3/H, Kr, Xe, and I from irradiated nuclear fuel have been determined as a function of temperature and gaseous environment. Vacuum outgassing and a flowing gas stream have been used to vary the gaseous environment. Vacuum outgassing released about 99% of the /sup 3/H and 20% of both Kr and Xe within a 3 h at 1500/sup 0/C. Similar results were obtained using a carrier gas of He containing 6% H/sub 2/. However, a carrier gas containing only He resulted in the release of approximately 80% of the /sup 3/H and 99% of both Kr and Xe. These results indicate that the release of these volatile fission products from irradiated nuclear fuel is a function of the chemical composition of the gaseous environment. The rate of tritium release increased with increasing temperature (1100 to 1500/sup 0/C) and with the addition of hydrogen to the gas stream. Using crushed UO/sub 2/ fuel without cladding and He as the carrier gas, Kr was completely released at 1500/sup 0/C in 2.5 h. Below 1350/sup 0/C, no Kr-Xe release was observed. Approximately 86% of the /sup 129/I and 95% of the cesium was released from a piece (3.9 g) of UO/sub 2/ fuel at 1500/sup 0/C in He. The zirconium cladding was observed to fracture during heat treatment. A large-scale thermal outgassing system was conceptually designed by the General Atomic Company from an engineering analysis of available experimental data. The direct cost of a 0.5 metric/ton day thermal outgassing system is estimated to be $1,926,000 (1982 dollars), including equipment, installation, instrumentation and controls, piping, and services. The thermal outgassing process was determined to be a technically feasible and cost-competitive process to remove tritium in the head-end portion of a LWR fuel reprocessing plant. Additional laboratory-scale development has been recommended.
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| 536 |
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|b AC06-76RL01830.
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| 650 |
|
7 |
|a Spent Fuels.
|2 local.
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| 650 |
|
7 |
|a Degassing.
|2 local.
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| 650 |
|
7 |
|a Fission Product Release.
|2 local.
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| 650 |
|
7 |
|a Uranium Dioxide.
|2 local.
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| 650 |
|
7 |
|a Iodine.
|2 local.
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| 650 |
|
7 |
|a Krypton 85.
|2 local.
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| 650 |
|
7 |
|a Quantity Ratio.
|2 local.
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| 650 |
|
7 |
|a Tritium.
|2 local.
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| 650 |
|
7 |
|a Beta Decay Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Chalcogenides.
|2 local.
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| 650 |
|
7 |
|a Elements.
|2 local.
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| 650 |
|
7 |
|a Energy Sources.
|2 local.
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| 650 |
|
7 |
|a Fuels.
|2 local.
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| 650 |
|
7 |
|a Halogens.
|2 local.
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| 650 |
|
7 |
|a Hours Living Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Hydrogen Isotopes.
|2 local.
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| 650 |
|
7 |
|a Intermediate Mass Nuclei.
|2 local.
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| 650 |
|
7 |
|a Isomeric Transition Isotopes.
|2 local.
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| 650 |
|
7 |
|a Isotopes.
|2 local.
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| 650 |
|
7 |
|a Krypton Isotopes.
|2 local.
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| 650 |
|
7 |
|a Light Nuclei.
|2 local.
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| 650 |
|
7 |
|a Materials.
|2 local.
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| 650 |
|
7 |
|a Nonmetals.
|2 local.
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| 650 |
|
7 |
|a Actinide Compounds.
|2 local.
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| 650 |
|
7 |
|a Nuclear Fuels.
|2 local.
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| 650 |
|
7 |
|a Nuclei.
|2 local.
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| 650 |
|
7 |
|a Beta-Minus Decay Radioisotopes.
|2 local.
|
| 650 |
|
7 |
|a Even-Odd Nuclei.
|2 local.
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| 650 |
|
7 |
|a Oxygen Compounds.
|2 local.
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| 650 |
|
7 |
|a Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Reactor Materials.
|2 local.
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| 650 |
|
7 |
|a Odd-Even Nuclei.
|2 local.
|
| 650 |
|
7 |
|a Uranium Compounds.
|2 local.
|
| 650 |
|
7 |
|a Oxides.
|2 local.
|
| 650 |
|
7 |
|a Uranium Oxides.
|2 local.
|
| 650 |
|
7 |
|a Years Living Radioisotopes.
|2 local.
|
| 650 |
|
7 |
|a Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities.
|2 edbsc.
|
| 650 |
|
7 |
|a Nuclear Fuel Cycle And Fuel Materials.
|2 edbsc.
|
| 700 |
1 |
|
|a Burger, L.L.
|4 aut.
|
| 700 |
1 |
|
|a Bray, L.A.
|4 aut.
|
| 700 |
1 |
|
|a Morgan, L.G.
|4 aut.
|
| 700 |
1 |
|
|a Baldwin, D.L.
|4 aut.
|
| 710 |
2 |
|
|a Pacific Northwest 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/servlets/purl/5942586/
|z Online Access
|
| 907 |
|
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|a .b74054624
|b 03-07-23
|c 07-05-13
|
| 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
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|s 2afeed2a-070c-5597-abac-30a9e8877188
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| 952 |
f |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:pnl-4488
|h Superintendent of Documents classification
|i web
|n 1
|
