A proposal to irradiate in the x-4 loop an instrumented uo2 fuel element operating in intermittent dryout and to measure the fission products rel

A proposal to irradiate in the x-4 loop an instrumented uo2 fuel element operating in intermittent dryout and to measure the fission products rel PDF Author: L. R. Bourque
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Languages : en
Pages : 0

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A proposal to irradiate in the x-4 loop an instrumented zircaloy clad uo2 fuel element with its sheath operation in intermittent dryout

A proposal to irradiate in the x-4 loop an instrumented zircaloy clad uo2 fuel element with its sheath operation in intermittent dryout PDF Author: R. D. Macdonald
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Category :
Languages : en
Pages : 0

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Addendum to proposal exp-fio-11701, a proposal to irradiate in the x-4 loop an instrumented zircaloy clad uo2 fuel element with its sheath operating in intermittent dryout

Addendum to proposal exp-fio-11701, a proposal to irradiate in the x-4 loop an instrumented zircaloy clad uo2 fuel element with its sheath operating in intermittent dryout PDF Author: R. D. Macdonald
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Category :
Languages : en
Pages : 0

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A proposal to irradiate a swept bruce-sized uo2 element in the x-4 loop of NRX to measure short-lived fission product release under normal and oxidizing conditions

A proposal to irradiate a swept bruce-sized uo2 element in the x-4 loop of NRX to measure short-lived fission product release under normal and oxidizing conditions PDF 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).

Proposal for an irradiation in intermittent dryout in the x-4 loop of a zircaloy sheathed uo2 fuel element with zircaloy clad thermocouples laser welded to the outside

Proposal for an irradiation in intermittent dryout in the x-4 loop of a zircaloy sheathed uo2 fuel element with zircaloy clad thermocouples laser welded to the outside PDF Author: L. R. Bourque
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Category :
Languages : en
Pages : 0

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A proposal to irradiate a swept instrumented uo2 element in the x-2 loop of NRX to measure short-lived fission product release during in-reactor high temperature transients

A proposal to irradiate a swept instrumented uo2 element in the x-2 loop of NRX to measure short-lived fission product release during in-reactor high temperature transients PDF Author: L. R. Bourque
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Category :
Languages : en
Pages : 0

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Addendum to a proposal to irradiate a swept instrumented uo2 element in the x-2 loop of NRX to measure short-lived fission product release during in-reactor high temperature transients

Addendum to a proposal to irradiate a swept instrumented uo2 element in the x-2 loop of NRX to measure short-lived fission product release during in-reactor high temperature transients PDF Author: I. J. Hastings
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Languages : en
Pages : 0

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A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements in periodic dryout in the x-4 loop

A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements in periodic dryout in the x-4 loop PDF Author: V. J. Langman
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Category :
Languages : en
Pages : 0

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Effects of Irradiation on Bulk UO2

Effects of Irradiation on Bulk UO2 PDF Author: John D. Eichenberg
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Category : Nuclear fuels
Languages : en
Pages : 198

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Irradiation of UO2 Fuel Rods

Irradiation of UO2 Fuel Rods PDF Author: John D. Eichenberg
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Category : Nuclear fuel rods
Languages : en
Pages : 28

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