Author: J. H. Kittel
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46
Book Description
Preliminary Experiments on Irradiation Cycling and Partial Beta-phase Irradiation of Uranium
Reactor Core Materials
Nuclear Science Abstracts
U.S. Government Research Reports
List
Atomic Industry Reporter: Technology reports
Author: Bureau of National Affairs (Arlington, Va.)
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1828
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1828
Book Description
Metallurgical Abstracts
Annual Report for ...
Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Ceramics
Languages : en
Pages : 176
Book Description
Publisher:
ISBN:
Category : Ceramics
Languages : en
Pages : 176
Book Description
Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 W/o Zirconium Alloys
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.
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.