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
Author: J. H. Kittel
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46
Book Description
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.
Thorium Fuel Cycle
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120
Book Description
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120
Book Description
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.