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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Category :
Languages : en
Pages : 0

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A proposal to irradiate deflected uo2 fuel elements clad in zr-2.5 wt percent nb and zr-1.2 wt perrcent cr-0.1 wt percent fe in superheated steam

A proposal to irradiate deflected uo2 fuel elements clad in zr-2.5 wt percent nb and zr-1.2 wt perrcent cr-0.1 wt percent fe in superheated steam PDF Author: G. R. Dimmick
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Category :
Languages : en
Pages : 0

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A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements in periodic dryout in the x-4 loop

A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements in periodic dryout in the x-4 loop PDF Author: V. J. Langman
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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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ISBN:
Category :
Languages : en
Pages : 0

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X-442 phase iv : a proposal to irradiate in dryout elements containing finned tubing, graphite discs and a graphite interlayer

X-442 phase iv : a proposal to irradiate in dryout elements containing finned tubing, graphite discs and a graphite interlayer PDF Author: G. R. Dimmick
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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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Zr-2 and zr-nb clad uo2 trefoil fuel irradiation in the x-7 organic loop

Zr-2 and zr-nb clad uo2 trefoil fuel irradiation in the x-7 organic loop PDF Author: A. K. Ip
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Languages : en
Pages : 0

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Proposal for an irradiation in intermittent dryout in the x-4 loop of a zircaloy sheathed uo2 fuel element with zircaloy clad thermocouples laser welded to the outside

Proposal for an irradiation in intermittent dryout in the x-4 loop of a zircaloy sheathed uo2 fuel element with zircaloy clad thermocouples laser welded to the outside PDF Author: L. R. Bourque
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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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ISBN:
Category :
Languages : en
Pages : 0

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