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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

Book Description


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

Book Description


Reactor Core Materials

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

Book Description


Nuclear Science Abstracts

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

Book Description


U.S. Government Research Reports

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

Book Description


List

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

Book Description


Atomic Industry Reporter: Technology reports

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

Book Description


Metallurgical Abstracts

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

Book Description


Annual Report for ...

Annual Report for ... PDF Author: Argonne National Laboratory
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

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.

Thorium Fuel Cycle

Thorium Fuel Cycle PDF 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.