A proposal to provide fission gas release information in irradiated uo2 fuel elements after a short re-irradiation at high heat ratings PDF Download
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Author: W. E. Laing
Publisher:
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Category :
Languages : en
Pages : 0
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Author: W. E. Laing
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Category :
Languages : en
Pages : 0
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Author: L. R. Bourque
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Category :
Languages : en
Pages : 0
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We propose to irradiate a trefoil assembly containing a bruce-sized, instrumented, stainless-steel-clad uo2 fuel element. the element will operate at a linear power of 60 kw/m in the x-4 loop for about five months. the element will have upper and lower gas lines attached, to allow sweeping of short-lived gaseous and volatile fission products from the fuel using a he-2 percent h2 carrier gas. species will be identified at a sample cylinder by gamma spectrometry. the element will operate under steady state conditions for most of the irradiation period, to obtain short-lived release data at a burnup typical of the maximum for current candu fuel. prior to the final shutdown we will introduce he-h2o as the carrier gas, to determine the additional short-lived release from uo2 under oxidizing conditions. this experiment is funded by the aecl-oh common development program (candev).
Author: T. J. Slosek
Publisher:
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Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 78
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Author:
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Category : Nuclear energy
Languages : en
Pages : 538
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Author: Gilbert E. Raines
Publisher:
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Category : Fission gases
Languages : en
Pages : 46
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Author:
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Category : Nuclear engineering
Languages : en
Pages : 1028
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Author: F. R. Campbell
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Category :
Languages : en
Pages : 0
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Author: British Nuclear Energy Society
Publisher: Thomas Telford Publishing
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Category : Technology & Engineering
Languages : en
Pages : 664
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Author: James B. Melehan
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ISBN:
Category : Fission gases
Languages : en
Pages : 60
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Author: R. D. Macdonald
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Category :
Languages : en
Pages : 0
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