Hydrogen Studies During PBF Severe Fuel Damage Tests PDF Download
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Languages : en
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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.
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Category :
Languages : en
Pages :
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Book Description
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: August W. Cronenberg
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Category :
Languages : en
Pages : 0
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Author: August W. Cronenberg
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Category : Light water reactors
Languages : en
Pages : 106
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Author:
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Category : Power resources
Languages : en
Pages : 354
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Category :
Languages : en
Pages : 0
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A comprehensive evaluation of the Severe Fuel Damage (SFD) Test 1-4 performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory is presented. Test SFD 1-4 was the fourth and final test in an internationally sponsored light water reactor severe accident research program, initiated by the US Nuclear Regulatory Commission. The overall technical objective of the test was to contribute to the understanding of fuel and control rod behavior, aerosol and hydrogen generation, and fission product release and transport during a high-temperature, severe fuel damage transient. A test bundle, comprised of 26 previously irradiated (36,000 MWd/MtU) pressurized water-reactor-type fuel rods, 2 fresh instrumented fuel rods, and 4 silver-indium-cadmium control rods, was surrounded by an insulating shroud and contained in a pressurized in-pile tube. The experiment consisted of a 1.3-h transient at a coolant pressure of 6.95 MPa in which the inlet coolant flow to the bundle was reduced to 0.6 g/s while the bundle fission power was gradually increased until dryout, heatup, cladding rupture, and oxidation occurred. With sustained fission power and heat from oxidation, temperatures continued to rise rapidly, resulting in zircaloy and control rod absorber alloy melting, fuel liquefaction, material relocation, and the release of hydrogen, aerosols, and fission products. The transient was terminated over a 2100-s time span by slowly reducing the reactor power and cooling the damaged bundle with argon gas. A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented. 40 refs., 160 figs., 31 tabs.
Author:
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Category : Nuclear fuel claddings
Languages : en
Pages : 376
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Author: Alan D. Knipe
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Category : Light water reactors
Languages : en
Pages : 364
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Author:
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ISBN:
Category : Power resources
Languages : en
Pages : 600
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Author:
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ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 374
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Author: David A. Petti
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Category : Government publications
Languages : en
Pages : 518
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