Addendum to proposal exp-dme-15901 : power boost of zr-1 wt percent nb clad fuel elements PDF Download

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Addendum to proposal exp-dme-15901 : power boost of zr-1 wt percent nb clad fuel elements

Addendum to proposal exp-dme-15901 : power boost of zr-1 wt percent nb clad fuel elements PDF Author: J. C. Wood
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Languages : en
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Addendum to proposal exp-dme-15901 : power boost of zr-1 wt percent nb clad fuel elements

Addendum to proposal exp-dme-15901 : power boost of zr-1 wt percent nb clad fuel elements PDF Author: J. C. Wood
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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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Languages : en
Pages : 0

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Addendum to proposal exp-NPD-4601 : irradiation of uo2 fuel clad with annealed zirconium - 2.5 percent wt percent niobium alloy in the NPD reactor to burnups approaching 240 mwh.kgu

Addendum to proposal exp-NPD-4601 : irradiation of uo2 fuel clad with annealed zirconium - 2.5 percent 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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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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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-2.5 wt percent nb clad fuel elements with canlub coating in a 28-element demountable bundle in the u-1 loop

A proposal to irradiate zr-2.5 wt percent nb clad fuel elements with canlub coating in a 28-element demountable bundle in the u-1 loop PDF Author: D. G. Hardy
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Languages : en
Pages : 0

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Addendum to proposal exp-NPD-4701. 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/kgu

Addendum to proposal exp-NPD-4701. 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/kgu PDF Author: R. D. Macdonald
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Languages : en
Pages : 0

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Addendum to proposal exp-dme-16401

Addendum to proposal exp-dme-16401 PDF Author: J. I. Hastings
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Languages : en
Pages : 0

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Addendum to the proposal to irradiate u-si-a1 fuel elements containing a surface layer of rapidly corroding fuel and a graphite layer between the fuel and the defected zr-2.5 wt percent nb sheath

Addendum to the proposal to irradiate u-si-a1 fuel elements containing a surface layer of rapidly corroding fuel and a graphite layer between the fuel and the defected zr-2.5 wt percent nb sheath PDF Author: A. M. Ross
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Languages : en
Pages : 0

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A proposal to irradiate zr-2.5 wt percent nb clad u-si-a1 fuel rods containing peripheral voidage

A proposal to irradiate zr-2.5 wt percent nb clad u-si-a1 fuel rods containing peripheral voidage PDF Author: P. J. Fehrenbach
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Languages : en
Pages : 0

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