Model to predict swelling, gas release, and densification in oxide fuels (AWBA development program) [electronic resource]

A model was developed to predict in-pile fission gas swelling, gas release, and densification in oxide fuels. This model considers fission gas behavior at the grain interior, on the grain boundaries, and at grain boundary edges under conditions of total gas bubble destruction by fission fragments an...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Alabama A & M University (Researcher), Bettis Atomic Power Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: West Mifflin, Pa. : Oak Ridge, Tenn. : Bettis Atomic Power Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1978.
Subjects:

MARC

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245 0 0 |a Model to predict swelling, gas release, and densification in oxide fuels (AWBA development program)  |h [electronic resource] 
260 |a West Mifflin, Pa. :  |b Bettis Atomic Power Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1978. 
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500 |a Dollins, C.C. 
520 3 |a A model was developed to predict in-pile fission gas swelling, gas release, and densification in oxide fuels. This model considers fission gas behavior at the grain interior, on the grain boundaries, and at grain boundary edges under conditions of total gas bubble destruction by fission fragments and partial gas bubble destruction. When gas bubble swelling on grain edges reaches 5 percent, it is assumed that gas tunnels form along the edges. Gas release takes place by migration of the gas in the grains and on the grain boundaries to the edge tunnels. Intergranular and intragranular densifications are considered. Densification takes place by vacancy boil-off due to thermal excitation and vacancy knockout by the passage of fission fragments through the pores. The migration rates of both vacancies and interstitials to pores are also calculated. Comparisons are made between the model and experimental data for swelling, gas release, and densification and found to be in reasonable agreement in most cases. 
536 |b EY-76-C-11-0014. 
650 7 |a Breeder Reactors.  |2 local. 
650 7 |a Thorium Compounds.  |2 local. 
650 7 |a Fuel Densification.  |2 local. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Transuranium Compounds.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Mathematical Models.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Uranium Compounds.  |2 local. 
650 7 |a Uranium Oxides.  |2 local. 
650 7 |a Lwbr Type Reactors.  |2 local. 
650 7 |a Plutonium Dioxide.  |2 local. 
650 7 |a Oxygen Compounds.  |2 local. 
650 7 |a Actinide Compounds.  |2 local. 
650 7 |a Plutonium Oxides.  |2 local. 
650 7 |a Uranium Dioxide.  |2 local. 
650 7 |a Fission Product Release.  |2 local. 
650 7 |a Plutonium Compounds.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Thorium Oxides.  |2 local. 
650 7 |a Thermal Reactors.  |2 local. 
650 7 |a Chalcogenides.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Alabama A & M University.  |4 res. 
710 2 |a Bettis Atomic Power 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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