Author: D. L. WardPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal for comparing the irradiation growth of clader uranum, uranium-1/2 at .percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: D. L. WardA proposal for comparing the irradiation growth of clader uranium- u-1/2 at .percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: W. N. MillerA proposal for comparing the irradiation growth of calder uranium, uranium - 1/2 at.percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: Irradiation Swelling of Uranium and Uranium Alloys
Author: Gordon G. BentlePublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 76
Book Description
Quantitative Correlation of Irradiation Growth with Preferred Orientation in Uranium
Author: William R. McDonellPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 32
Book Description
"Pin-cushion" Irradiation Tests of Uranium-chromium Alloys
Author: S. H. PainePublisher:
ISBN:
Category : Chromium alloys
Languages : en
Pages : 46
Book Description
Irradiation tests on small pins of wrought and heat-treated U235-Cr alloys mounted in special heat transfer blocks or ''cushions'' are described. Three compositions, estimated at 0.03, 0.07, and 0.22 wt.% Cr, were tested in three metallurgical conditions: alpha-annealed, beta-quenched, and isothermally transformed. Radiation damage to the specimens having the first two heat treatments was very similar to that observed in unalloyed uranium of comparable history, and the isothermally treated specimens were similar to beta-annealed uranium in behavior. In spite of this essentially null result, which is associated with failure to obtain grain refinement in the specimens, there is evidence that under proper conditions chromium additions to uranium may be beneficial.
Irradiation of Extrusion-clad Uranium-2 W/o Zirconium Alloy for EBR-1, Mark III
Author: J. H. KittelPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 40
Book Description
The fuel material specified for the Mark III core of EBR-I was uranium-2 wt. % zirconium alloy coextruded with Zircaloy-2 cladding. From previous work on swaged or rolled uranium-2 wt% zirconium alloy, it was anticipated that the extruded alloy would be dimensionally unstable under irradiation unless stabilized by suitable heat treatment. In order to determine an effective heat treatment, irradiation studies were made on both clad and unclad extruded uranium-2 wt.% zirconium alloy specimens at irradiation temperature estimated at 200 to 750 deg C. The irradiation specimens included material with three different heat treatments, selected on the basis of previous studies, and material transient melted in its cladding. For unclad specimens, it was found that the irradiation temperature strongly influenced the various irradiation growth rates resulting from different heat treatments. Growth rates of the clad specimens were relatively insensitive to either irradiation temperature or prior heat treatment. An exception was the transient-melted material, which shortened under irradiation. The cladding had only limited ability to restrain the swelling rates of specimens irradiated at the more elevated temperatures. Clad transient-melted material was found to be most resistant to high-temperature swelling under irradiation. The results of the present study combined with observations in earlier investigations resulted in a recommendation that the reference heat treatment for the core consist of gamma solution at 800 deg C followed by isothermal transformation at 690 deg C.
Irradiation Behavior of Uranium Carbide Fuels
Author: D. I. SinizerPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 52
Book Description
The Effects of Irradiation on the Tensile Properties of Uranium
Author: R. E. HueschenPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 60
Book Description
Effects of Rolling and Heat Treatment on Anisotropic Irradiation Growth of Uranium
Author: J. H. KittelPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 38
Book Description
An investigation was made to determine the effect of rolling temperature, roll pass design, amount of reduction, and heat treatment before and after rolling on the anisotropic growth rate of uranium under irradiation. The growth rate was found to increase with decreasing rolling temperature and with increasing reduction of area at 300 deg C. The rate of elongation was proportional to the amount of (010) component present or, where shortening occurred, to the amount of (100) component. Oval-edge-oval roll passes resulted in somewhat higher irradiation growth rates than did round roll passes. Recrystallization after rolling effectively reduced the irradiation growth rate of uranium rolled at temperatures of 500 deg C and lower. Irradiation caused length shortening in uranium which was beta quenched after being round-rolled at temperatures of 400 deg C and above, and which was beta quenched after being oval- rolled at temperatures of 300 deg C and above.