Preliminary Experiments on Irradiation Cycling and Partial Beta-phase Irradiation of Uranium

Preliminary Experiments on Irradiation Cycling and Partial Beta-phase Irradiation of Uranium PDF Author: J. H. Kittel
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46

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Reactor Core Materials

Reactor Core Materials PDF Author:
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ISBN:
Category : Nuclear reactors
Languages : en
Pages : 316

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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Category : Nuclear energy
Languages : en
Pages : 1396

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U.S. Government Research Reports

U.S. Government Research Reports PDF Author:
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Category : Science
Languages : en
Pages : 144

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List

List PDF Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 564

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Atomic Industry Reporter: Technology reports

Atomic Industry Reporter: Technology reports PDF Author: Bureau of National Affairs (Arlington, Va.)
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Category : Nuclear energy
Languages : en
Pages : 1828

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Metallurgical Abstracts

Metallurgical Abstracts PDF Author:
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Category : Metallurgy
Languages : en
Pages : 536

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Annual Report for ...

Annual Report for ... PDF Author: Argonne National Laboratory
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Category : Ceramics
Languages : en
Pages : 176

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Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 W/o Zirconium Alloys

Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 W/o Zirconium Alloys PDF Author: J. H. Kittel
Publisher:
ISBN:
Category : Heat resistant alloys
Languages : en
Pages : 40

Book Description
An investigation of the effects of irradiation on uranium containing 0.52 and 1.62 w/o zirconium was made. Specimens of wrought material, variously heat treated, were studied as well as castings of the alloys. It was found that, although the wrought and heat-treated alloys were reportedly stable under thermal cycling, they elongated rapidly under irradiation. The best material studied was the 1.62% alloy in the as-cast condition. It was found to increase in length initially at a rate of about 5% per a/o burnup, after which the rate steadily diminished. Up to burnups of at least 5.3 a/o it retained a smooth surface. Two specimens of the cast 1.62% alloy, one irradiated to 2.1 a/o burnup at a calculated central temperature of 690 deg C and the other irradiated to 5.3 at.% burnup at a calculated central temperature of 620 deg C, swelled and increased in volume with the formation of a large central void surrounded by highly porous metal. The critical swelling temperature of urauium--1.62 w/o zirconium alloy was found to lie between 300 and 620 deg C, with some indications that it may be near 500 deg C.

Bibliography of Scientific and Industrial Reports

Bibliography of Scientific and Industrial Reports PDF Author:
Publisher:
ISBN:
Category : Technology
Languages : en
Pages : 448

Book Description