Author: P. J. FehrenbachPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal to irradiate three zirconium alloy clad uo2 fuel elements in the x-6 loop of NRX using the he-3 power cycling facility
Author: P. J. FehrenbachScientific and Technical Aerospace Reports
Author: Irradiation of UO2 Fuel Rods
Author: John D. EichenbergPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 28
Book Description
Addendum to proposal exp-NRX-53901 : the irradiation of fuel elements containing unirradiated uo2 pellets clad in zirconium alloy tubes previously irradiated to 8 x 10 sup(20) n/cm2
Author: R. D. MacdonaldA proposal to irradiate zircaloy clad uo2 fuel elements in the x-3 loop at average linear heat outputs of 30 and 60 kw/m and burnups up to 400 mwh/kg u
Author: R. D. MacdonaldA proposal for an irradiation to compare argon and air-filled zircaloy-4 clad fuel elements in the universal irradiation facility (uif) of the x-6 loop
Author: R. CarbonneauThe irradiation of stainless steel clad uo2 fuel elements in the NRX x-4 steam-cooled loop. (i.e. 260/408). a final proposal to irradiate fuel elements containing annular pellets. appendix : a preliminary proposal for the irradiation of 0.57 in. diameter stainless steel tubes for subsequent out-of-pile Creep rupture tests
Author: H. N. JonesA proposal to irradiate zircaloy clad tho2-uo2 fuel elements in the x-3 loop at average linear heat outputs of 70 kw/m and to burnups of 500 mwh/kg u
Author: R. D. MacdonaldA proposal to irradiate zircaloy clad uo2 fuel elements at low power in x-5 for use in future power cycling experiments
Author: P. J. FehrenbachA 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
Author: L. R. BourquePublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
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).