Release of volatile fission products from uranium dioxide [electronic resource]

Post-irradiation anneal experiments have been used to determine the release of iodine and tellurium from lightly irradiated UO₂ samples maintained at stoichiometry. The applicability of the equivalent-sphere model of diffusion to release of fission gases has been tested. Diffusion coefficients and a...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Lawrence Berkeley Laboratory (Researcher), Lawrence Berkeley National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Berkeley, Calif. : Oak Ridge, Tenn. : Lawrence Berkeley National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1983.
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MARC

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245 0 0 |a Release of volatile fission products from uranium dioxide  |h [electronic resource] 
260 |a Berkeley, Calif. :  |b Lawrence Berkeley National Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1983. 
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520 3 |a Post-irradiation anneal experiments have been used to determine the release of iodine and tellurium from lightly irradiated UO₂ samples maintained at stoichiometry. The applicability of the equivalent-sphere model of diffusion to release of fission gases has been tested. Diffusion coefficients and activation energies have been evaluated. The diffusion coefficient of ¹³²Te at 1400°C was found to be of an order-of-magnitude larger than that of ¹³¹I. This result may be of importance for an understanding of the pellet-cladding interaction and for a better evaluation of the source term for fission-product release under accident conditions. Qualitatively, the influence of the stoichiometry on the release of ¹³³Xe, ¹³¹I, and ¹³²Te has been established. 
536 |b AC03-76SF00098. 
650 7 |a Days Living Radioisotopes.  |2 local. 
650 7 |a Beta Decay Radioisotopes.  |2 local. 
650 7 |a Iodine 131.  |2 local. 
650 7 |a Uranium Compounds.  |2 local. 
650 7 |a Beta-minus Decay Radioisotopes.  |2 local. 
650 7 |a Even-even Nuclei.  |2 local. 
650 7 |a Fuel-cladding Interactions.  |2 local. 
650 7 |a Isotopes.  |2 local. 
650 7 |a Actinide Compounds.  |2 local. 
650 7 |a Oxygen Compounds.  |2 local. 
650 7 |a Stoichiometry.  |2 local. 
650 7 |a Uranium Dioxide.  |2 local. 
650 7 |a Annealing.  |2 local. 
650 7 |a Iodine Isotopes.  |2 local. 
650 7 |a Intermediate Mass Nuclei.  |2 local. 
650 7 |a Tellurium 132.  |2 local. 
650 7 |a Odd-even Nuclei.  |2 local. 
650 7 |a Tellurium Isotopes.  |2 local. 
650 7 |a Uranium Oxides.  |2 local. 
650 7 |a Post-irradiation Examination.  |2 local. 
650 7 |a Heat Treatments.  |2 local. 
650 7 |a Fission Product Release.  |2 local. 
650 7 |a Internal Conversion Radioisotopes.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Nuclei.  |2 local. 
650 7 |a Chalcogenides.  |2 local. 
650 7 |a Radioisotopes.  |2 local. 
650 7 |a Nuclear Fuel Cycle And Fuel Materials.  |2 edbsc. 
650 7 |a Materials Science.  |2 edbsc. 
650 7 |a General Studies Of Nuclear Reactors.  |2 edbsc. 
710 2 |a Lawrence Berkeley Laboratory.  |4 res. 
710 2 |a Lawrence Berkeley National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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