Author: R. J. BeaverPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 38
Book Description
An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-aluminum Alloy Research Reactor Fuel Plates
Author: R. J. BeaverPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 38
Book Description
AN EVALUATION OF THE URANIUM CONTAMINATION ON THE SURFACES OF ALCLAD URANIUM-ALUMINUM ALLOY RESEARCH REACTOR FUEL PLATES.
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding. This diffusion is likely because of the 600 deg C heat treatments used in the conventional fabrication process. Uranium determinations based on neutron activation analysis of machined layers from fuel plate surfaces showed that rolling-mill equipment, contaminated with highly enriched uranium, was responsible for transferring as much as 180 ppm U to plate surfaces. By careful practice where cleanliness is emphasized, surface contamination can be reduced to 0.6 ppm U/sup 235/. The residue remaining on the plate surface may be accounted for by diffusion of uranium from the fuel alloy into and through the cladding of the fuel plate. Data obtained from preliminary diffusion studies permitted a good estimate to be made of the diffusion coefficient of uranium into aluminum at 600 deg C: 2.5 x 10/sup -8/ cm//sec. To minimize diffusion while the plate-type aluminum-base research reactor fuel element is being processed, heat treatments at 600 deg C should be limited to 2.5 hr. The uranium contamination on the surfaces of the finished fuel plates should then be less than 0.6 ppm U / sup 235/ . This investigation also revealed that the solubility limit of uranium in aluminum at 600 deg C is approx 60 ppm. (auth).
Nuclear Science Abstracts
Author: Reactor Materials
Author: Uranium Metallurgy: Uranium corrosion and alloys
Author: Walter D. WilkinsonPublisher:
ISBN:
Category : Uranium
Languages : en
Pages : 756
Book Description
TID.
Author: Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory
Author: Oak Ridge National LaboratoryPublisher:
ISBN:
Category : Government publications
Languages : en
Pages : 256
Book Description
Summaries of Fuels and Materials Development Programs
Author: William L. R. RicePublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 278
Book Description
Summaries of Fuels and Materials Development Program
Author: William L. R. RicePublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 286
Book Description
Irradiation of an Aluminum Alloy-clad, Aluminum-uranium Alloy-fueled Plate
Author: A. P. GavinPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52
Book Description
Irradiation tests of an aluminum-alloy-clad aluminum -uranium alloy- fueled plate were discontinued due to cladding failure after a maximum burnup of 58%. Cause of the failure was local corrosion of the aluminum alloy. Swelling was observed which was attributed to the combination of high burnup and high fuel temperatures.