An Assessment of Hydrogen Generation for the PBF Severe Fuel Damage Scoping and 1-1 Test PDF Download
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Author: August W. Cronenberg
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 106
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Book Description
Author: August W. Cronenberg
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 106
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Book Description
Author: August W. Cronenberg
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: Alan D. Knipe
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 364
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Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1020
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Author:
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ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 374
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Author: T. Van Der Kaa
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Category :
Languages : en
Pages : 0
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Book Description
The scdap/modo/version 6 computer code was used to predict the behavior of the fuel bundle during the severe fuel damage (sfd) test 1-3. test sfd 1-3 simulates severe core damage resulting from a small break loss-of-coolant accident without emergency core coolant injection. the test will be characterized by boiloff of the coolant in the core, slow core heatup to 1600 k, followed by rapid heatup of the core to over 2400 k driven by rapid oxidation of the fuel cladding. the analytical predictions include thermal-hydraulic behavior of the core, power and temperature history, oxidation and hydrogen generation, dissolution of uo2, and fission product release. the results indicate that, if performed as planned, test sfd 1-3 will meet the test objectives.
Author: M. Gasparini
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Category :
Languages : en
Pages : 0
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The scdap version 8 computer code was used to predict the behavior of the fuel bundle during the severe fuel damage (sfd) test 1-4. test sfd 1-4 is intended to simulate severe core damage resulting from a small break, loss-of-coolant accident without emergency core coolant injection. the test will be characterized by boiloff of the coolant in the bundle, slow heatup (o.4 k/s) to 1200 k, faster heatup (1.3 k/s) to 1600 k, and very rapid heatup of the fuel to over 2400 k driven by rapid oxidation of the cladding. analytical predictions include thermal-hydraulic behavior, power and temperature history, oxidation and hydrogen generation, cladding deformation and failure, uo2 dissolution and relocation, and fission product release. the results indicate that, if performed as planned, test sfd 1-4 will meet the test objectives.
Author: J. N. Lillington
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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The paper presents an analysis of the pbf severe fuel damage scoping test performed at eg&g idaho falls using scdap. the performance of thermal-hydraulic and oxidation models in the code in the context of this experiment is assessed. the main pehnomena predicted by scdap are presented and in general agreement with experiment is good. the most interesting feature of the experiment, the final excursion, is predicted to be consistent with a thermal-hydraulic feed-back resulting from a deterioration in bundle cooling.
Author:
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Category :
Languages : en
Pages :
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The PBF Severe Fuel Damage tests will provide a unique opportunity to address several reactor safety issues. These experiments will simulate severe accidents which include fuel behavior similar to the TMI accident. Rod damage mechanisms, fuel rod fragmentation, rubble bed formation, hydrogen generation and fission product release are among the important phenomena which will be investigated. The on-line hydrogen measurements, supplemented with analyses of grab samples will provide data to evaluate zircaloy oxidation models and define hydrogen behavior during accidents.
Author:
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ISBN:
Category : Nuclear power plants
Languages : en
Pages : 544
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