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20080830000000.0 |
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100527e19830901ilu s| f1|||||eng|d |
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|a (TOE)ost5532885
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|a (TOE)5532885
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|a TOE
|c TOE
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| 049 |
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:conf-8310144-3-rev
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|a E 1.99:conf-8310144-3-rev
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| 245 |
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|a Mechanistic prediction of fission product release under normal and accident conditions
|h [electronic resource] :
|b key uncertainties that need better resolution.
|
| 260 |
|
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|a Argonne, Ill. :
|b Argonne National Lab ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1983.
|
| 300 |
|
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|a Pages: 44 :
|b digital, PDF file.
|
| 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 the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 09/01/1983.
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| 500 |
|
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|a "conf-8310144-3-rev."
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| 500 |
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|a "DE84003715"
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| 500 |
|
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|a Specialists' workshop on fission gas behavior in safety experiments, Cadarache, France, 5 Oct 1983.
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| 500 |
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|a Rest, J.
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| 520 |
3 |
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|a A theoretical model has been used for predicting the behavior of fission gas and volatile fission products (VFPs) in UO₂-base fuels during steady-state and transient conditions. This model represents an attempt to develop an efficient predictive capability for the full range of possible reactor operating conditions. Fission products released from the fuel are assumed to reach the fuel surface by successively diffusing (via atomic and gas-bubble mobility) from the grains to grain faces and then to the grain edges, where the fission products are released through a network of interconnected tunnels of fission-gas induced and fabricated porosity. The model provides for a multi-region calculation and uses only one size class to characterize a distribution of fission gas bubbles.
|
| 536 |
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|b W-31-109-ENG-38.
|
| 650 |
|
7 |
|a Beta Decay Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Days Living Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Iodine 131.
|2 local.
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| 650 |
|
7 |
|a Iodine 133.
|2 local.
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| 650 |
|
7 |
|a Uranium Compounds.
|2 local.
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| 650 |
|
7 |
|a Beta-minus Decay Radioisotopes.
|2 local.
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| 650 |
|
7 |
|a Time Dependence.
|2 local.
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| 650 |
|
7 |
|a Isotopes.
|2 local.
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| 650 |
|
7 |
|a Actinide Compounds.
|2 local.
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| 650 |
|
7 |
|a Oxygen Compounds.
|2 local.
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| 650 |
|
7 |
|a Uranium Dioxide.
|2 local.
|
| 650 |
|
7 |
|a Temperature Dependence.
|2 local.
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| 650 |
|
7 |
|a Fuel Elements.
|2 local.
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| 650 |
|
7 |
|a Fuel Rods.
|2 local.
|
| 650 |
|
7 |
|a Iodine Isotopes.
|2 local.
|
| 650 |
|
7 |
|a Intermediate Mass Nuclei.
|2 local.
|
| 650 |
|
7 |
|a Odd-even Nuclei.
|2 local.
|
| 650 |
|
7 |
|a Crystal Structure.
|2 local.
|
| 650 |
|
7 |
|a Uranium Oxides.
|2 local.
|
| 650 |
|
7 |
|a Burnup.
|2 local.
|
| 650 |
|
7 |
|a Swelling.
|2 local.
|
| 650 |
|
7 |
|a Fission Product Release.
|2 local.
|
| 650 |
|
7 |
|a Reactor Components.
|2 local.
|
| 650 |
|
7 |
|a Oxides.
|2 local.
|
| 650 |
|
7 |
|a Microstructure.
|2 local.
|
| 650 |
|
7 |
|a Nuclei.
|2 local.
|
| 650 |
|
7 |
|a Radioisotopes.
|2 local.
|
| 650 |
|
7 |
|a Chalcogenides.
|2 local.
|
| 650 |
|
7 |
|a Hours Living Radioisotopes.
|2 local.
|
| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
|
| 710 |
2 |
|
|a Argonne 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/servlets/purl/5532885-VSBBBW/
|z Online Access
|
| 907 |
|
|
|a .b60016371
|b 03-06-23
|c 05-30-10
|
| 998 |
|
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|a web
|b 05-30-10
|c f
|d m
|e p
|f eng
|g ilu
|h 0
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
f |
|i 7fa723f3-1803-55bd-96db-ff03b0b7d486
|s b8e4c24b-74d6-57a5-8ea1-8a95c8c5a350
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-8310144-3-rev
|h Superintendent of Documents classification
|i web
|n 1
|
