Pbf severe fuel damage test series test sfd 1-4 experiment prediction PDF Download
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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: M. Gasparini
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ISBN:
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: T. Van Der Kaa
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Category :
Languages : en
Pages : 0
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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: David A. Petti
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Category : Government publications
Languages : en
Pages : 512
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Author: Z. R. Martinson
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Category :
Languages : en
Pages : 0
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This document describes the experiment operating specifications for test severe fuel damage 1-3 (sfd 1-3) to be conducted in the power burst facility (pbf) at the idaho national engineering laboratory (inel) as part of the nuclear regulatory commission's severe fuel damage research program. the overall experiment requirements and objectives for phase 1 of the sfd test series are described in the sfd experiment requirements document. the experiment specifications for test sfd 1-3 are described in the sfd experiment specification document and the pretest predictions are presented in the test sfd 1-3 experiment prediction document. the sfd test series objectives are to provide fuel bundle behavior data under severe high temperature flow starvation conditions. the objectives of test sfd 1-3 are to simulate the core heatup during the three mile island unit 2 accident and to characterize fuel rod damage, fission product release, and hydrogen production using high burnup test rods. a rod bundle consisting of 26 irradiated test fuel rods, two fully-instrumented fresh fuel rods, and four control rod guide thimbles will be tested in test sfd 1-3. the test will begin with a power calibration and preconditioning phase in which the bundle will be operated at a steady state bundle power of approximately 225 kw. after a 2 to 8 day shutdown period, high bundle temperatures of 2400 k will be obtained by operating with a bundle flow rate of 0.6 g/s and a maximum bundle power up to approximately 70 kw. the test will be terminated by a slow cooldown of the bundle with argon gas.
Author:
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Category : Nuclear fuel claddings
Languages : en
Pages : 374
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Category : Nuclear fuel claddings
Languages : en
Pages : 376
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Author: K. Mccormick
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Category :
Languages : en
Pages : 0
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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: Zoel R. Martinson
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ISBN:
Category :
Languages : en
Pages : 0
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Author:
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ISBN:
Category : Power resources
Languages : en
Pages : 998
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