Zr-2.5 wt percent nb clad fuel elements containing annular high density uo2 pellets with and without graphite discs irradiated to a burnup of 700 mwh/kgu in the x-5 loop PDF Download

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Zr-2.5 wt percent nb clad fuel elements containing annular high density uo2 pellets with and without graphite discs irradiated to a burnup of 700 mwh/kgu in the x-5 loop

Zr-2.5 wt percent nb clad fuel elements containing annular high density uo2 pellets with and without graphite discs irradiated to a burnup of 700 mwh/kgu in the x-5 loop PDF Author: R. D. Macdonald
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ISBN:
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Languages : en
Pages : 0

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Zr-2.5 wt percent nb clad fuel elements containing annular high density uo2 pellets with and without graphite discs irradiated to a burnup of 700 mwh/kgu in the x-5 loop

Zr-2.5 wt percent nb clad fuel elements containing annular high density uo2 pellets with and without graphite discs irradiated to a burnup of 700 mwh/kgu in the x-5 loop PDF Author: R. D. Macdonald
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Irradiation of zr-2.5 wt percent nb sheathed fuel bundles containing graphite discs between pellets of annular high density uo2 fuel in the NPD reactor to burnups approaching 240 mwh/kg u

Irradiation of zr-2.5 wt percent nb sheathed fuel bundles containing graphite discs between pellets of annular high density uo2 fuel in the NPD reactor to burnups approaching 240 mwh/kg u PDF Author: R. D. Macdonald
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Category :
Languages : en
Pages : 0

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Fabrication data for thirty-six zr-2.5 wt percent nb clad fuel elements containing annular uo2 pellets

Fabrication data for thirty-six zr-2.5 wt percent nb clad fuel elements containing annular uo2 pellets PDF Author: R. J. Stack
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Languages : en
Pages : 0

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A proposal to examine the defect behaviour of a zr-2.5 wt percent nb clad element containing u-si-a1 fuel rods with graphite discs impregnated with uo2 between rods

A proposal to examine the defect behaviour of a zr-2.5 wt percent nb clad element containing u-si-a1 fuel rods with graphite discs impregnated with uo2 between rods PDF Author: M. B. Watson
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Category :
Languages : en
Pages : 0

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Irradiation of uo2 fuel clad with annealed zirconium-2.5 wt percent niobium alloy in the NPD reactor to burnups approaching 240 mwh/kgu

Irradiation of uo2 fuel clad with annealed zirconium-2.5 wt percent niobium alloy in the NPD reactor to burnups approaching 240 mwh/kgu PDF Author: C. E. Coleman
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Languages : en
Pages : 0

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The 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

The 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 PDF Author: H. N. Jones
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Languages : en
Pages : 0

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A comparison of the irradiation behaviour of zircaloy clad uo2 fuel elements with and without thin discs of graphite molybdenum or niobium between pellets

A comparison of the irradiation behaviour of zircaloy clad uo2 fuel elements with and without thin discs of graphite molybdenum or niobium between pellets PDF Author: R. D. Macdonald
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Languages : en
Pages : 0

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X-442 phase v : a proposal for an irradiation of finned zr-2.5 wt percent nb clad uo2 fuel elements in dryout

X-442 phase v : a proposal for an irradiation of finned zr-2.5 wt percent nb clad uo2 fuel elements in dryout PDF Author: G. R. Dimmick
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Languages : en
Pages : 0

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A proposal to irradiate zr-2.5 wt.percent nb clad fuel elements and corrosion specimens in x-6 loop

A proposal to irradiate zr-2.5 wt.percent nb clad fuel elements and corrosion specimens in x-6 loop PDF Author: E. G. Mcvey
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Languages : en
Pages : 0

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A proposal to irradiate zr-1 wt percent nb clad fuel elements to test the low power soak-power boost behaviour and to produce specimens for an evaluation of the stress corrosion cracking resistance of the alloy in iodine vapour

A proposal to irradiate zr-1 wt percent nb clad fuel elements to test the low power soak-power boost behaviour and to produce specimens for an evaluation of the stress corrosion cracking resistance of the alloy in iodine vapour PDF Author: J. C. Wood
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Category :
Languages : en
Pages : 0

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