Addendum to a proposal to power ramp previously irradiated zircaloy-4 uo2 fuel elements and to study the in-reactor post-defect behaviour

Addendum to a proposal to power ramp previously irradiated zircaloy-4 uo2 fuel elements and to study the in-reactor post-defect behaviour PDF Author: B. J. Lewis
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Languages : en
Pages : 0

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A proposal to power ramp previously irradiated zircaloy-4/uo2 fuel elements and to study the in-reactor post-defect behaviour

A proposal to power ramp previously irradiated zircaloy-4/uo2 fuel elements and to study the in-reactor post-defect behaviour PDF Author: N. V. Ivanoff
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Languages : en
Pages : 0

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A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements at post-dryout sheath temperatures in the 625-675 degrees c range in the x-4 loop

A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements at post-dryout sheath temperatures in the 625-675 degrees c range in the x-4 loop PDF Author: V. J. Langman
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Languages : en
Pages : 0

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A proposal to power cycle irradiated, zircaloy-clad, uo2 fuel elements using an in-reactor diameter measuring rig (irdmr) and the he-3 system in

A proposal to power cycle irradiated, zircaloy-clad, uo2 fuel elements using an in-reactor diameter measuring rig (irdmr) and the he-3 system in PDF Author: P. J. Fehrenbach
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Languages : en
Pages : 0

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Hot cell examination of a previously irradiated and then power ramped to defect zircaloy-4/uo2 fuel element job no. 917

Hot cell examination of a previously irradiated and then power ramped to defect zircaloy-4/uo2 fuel element job no. 917 PDF Author: R. E. Moeller
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Category :
Languages : en
Pages : 0

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A proposal to study the effect of power ramp conditions on the dimensional stability of zircaloy-clad uo2 fuel elements

A proposal to study the effect of power ramp conditions on the dimensional stability of zircaloy-clad uo2 fuel elements PDF Author: P. J. Fehrenbach
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Languages : en
Pages : 0

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Proposal for power ramping two canflex uo2 fuel bundles irradiated at low power to an outer element burnup of ~ 150 mwh/kgu in the reactor

Proposal for power ramping two canflex uo2 fuel bundles irradiated at low power to an outer element burnup of ~ 150 mwh/kgu in the reactor PDF Author: M.R. Floyd
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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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Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR

Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR PDF Author: C. N. Spalaris
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Category : Boiling water reactors
Languages : en
Pages : 80

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Fabrication details for five zircaloy-4 clad fuel elements containing low density uo2 fuel pellets for irradiation in the NRU reactor

Fabrication details for five zircaloy-4 clad fuel elements containing low density uo2 fuel pellets for irradiation in the NRU reactor PDF Author: J. D. Craigie
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Languages : en
Pages : 0

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