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-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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Category :
Languages : en
Pages : 0

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Final proposal for the irradiation of long elements (12 ins. fuel) and zirconium alloy corrosion specimens in the x-4 steam loop

Final proposal for the irradiation of long elements (12 ins. fuel) and zirconium alloy corrosion specimens in the x-4 steam loop PDF Author: J. Molloy
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Category :
Languages : en
Pages : 0

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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Category : Nuclear energy
Languages : en
Pages : 516

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Pre-irradiation data report on fabrication of zircaloy-2 and zirconium-2.5 percent niobium clad fuel elements for irradiation in the x-6 loop

Pre-irradiation data report on fabrication of zircaloy-2 and zirconium-2.5 percent niobium clad fuel elements for irradiation in the x-6 loop PDF Author: G. K. Wong
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Languages : en
Pages : 0

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Effects of High Burnup on Zircaloy-clad, Bulk UO2, Plate Fuel Element Samples

Effects of High Burnup on Zircaloy-clad, Bulk UO2, Plate Fuel Element Samples PDF Author: R. C. Daniel
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Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 294

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Fabrication data for twelve demountable zr-1.0 wt percent nb clad fuel elements to test the low power soak-boost behaviour and stress corrosion cracking resistance of the alloy

Fabrication data for twelve demountable zr-1.0 wt percent nb clad fuel elements to test the low power soak-boost behaviour and stress corrosion cracking resistance of the alloy PDF Author: R. J. Stack
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Category :
Languages : en
Pages : 0

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A proposal for the irradiation of an instrumented trefoil containing 304l, zr-cr-fe and zr-2.5 wt percent nb clad fuel at up to 500 degrees c sheath temperature in dryout in x-4

A proposal for the irradiation of an instrumented trefoil containing 304l, zr-cr-fe and zr-2.5 wt percent nb clad fuel at up to 500 degrees c sheath temperature in dryout in x-4 PDF Author: G. R. Dimmick
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Category :
Languages : en
Pages : 0

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Proposal to irradiate u-si-al alloys clad in zr-2.5 wt percent nb in pressurized water

Proposal to irradiate u-si-al alloys clad in zr-2.5 wt percent nb in pressurized water PDF Author: C. D. Chomski
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Languages : en
Pages : 0

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A proposal to irradiate mechanical test specimens of zr-1 wt percent nb fuel sheathing

A proposal to irradiate mechanical test specimens of zr-1 wt percent nb fuel sheathing PDF Author: D. O. Northwood
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Languages : en
Pages : 0

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Irradiation performance of canlub coated zr-2.5 wt percent nb fuel cladding in the x-4 loop

Irradiation performance of canlub coated zr-2.5 wt percent nb fuel cladding in the x-4 loop PDF Author: J. C. Wood
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Category :
Languages : en
Pages : 0

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