Author: P. F. HaughtonPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 38
Book Description
An Improved Method of Measuring Uranium Concentration in Uranium-aluminum Alloy by Gamma Counting
Author: P. F. HaughtonPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 38
Book Description
Gamma Count Estimation of Enhanced Uranium Concentration in Solutions
Author: W. B. WrightPublisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 16
Book Description
Papers Presented at the Reactor Fuel Measurement Techniques Symposium
Author: U.S. Atomic Energy CommissionPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 212
Book Description
Determination of 238U, 235U, and 237Np in Aluminum Metal by Gamma Spectrometry
Author: J. C. WilliamsPublisher:
ISBN:
Category : Aluminum
Languages : en
Pages : 32
Book Description
The Use of High-efficiency Gamma Counting in Conjunction with Beta Counting for Discrimination Between Thorium and Uranium
Author: Robert H. RoethlisbergerPublisher:
ISBN:
Category : Beta rays
Languages : en
Pages : 16
Book Description
Use of the high-pressure gamma chamber and vibrating reed electrometer to measure gamma activity and the end window Geiger counter to measure beta activity has permitted discrimination between activity due to thorium and that due to uranium so that the thorium and uranium content of ore samples can be determined radiometrically within a factor of 2 and usually within 15 per cent.
AEC Research and Development Report
Author: Atomic Energy CommissionPublisher:
ISBN:
Category :
Languages : en
Pages : 100
Book Description
Analysis Methods and Performance of an Automated System for Measuring Both Concentration and Enrichment of Uranium in Solutions
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 9
Book Description
For the 1992 INNM Meeting, we reported on an automated system under development for measuring both concentration and enrichment of uranium in solutions. In this paper, we report on measurement methods, ysis algorithms, and performance of the delivered system. The uranium concentration is measured by a transmission-corrected x-ray fluorescence method. Cobalt-57 is the fluorescing source and a combined 153Gd and 57Co source is used for the transmission measurements. Corrections are made for both the absorption of the exciting 57Co gamma rays and the excited uranium x-rays. The 235U concentration is measured by a transmission-corrected method, which employs the 185.7-keV gamma ray of 235U and a transmission source of 75Se to make corrections for the self-absorption of the 235U gamma rays in the solution samples. Both measurements employ high-resolution gamma-ray spectrometry and use the same 50-ml sample contained in a custom-molded, flat-bottomed, polypropylene bottle. Both measurements are intended for uranium solutions with concentrations ≥0.1 g U/l although at higher enrichments the passive measurement will be even more sensitive.
Bibliography of Non-destructive Assay Methods for Nuclear Material Safeguards
Author: United States. Division of Nuclear Materials SecurityPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 100
Book Description
Author: 
Author: