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{sup 235}U accountability measurements on small samples [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1991.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
11 pages : digital, PDF file
Additional Creators
Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Savannah River Site (SRS) is improving uranium accountability at its fuel fabrication facility through measurements of ²³⁵U in samples taken from uranium/aluminum alloy melts. Since area personnel desired a method that would minimize mixed waste, low volume samples are prepared from dissolutions of production melt grab samples. The solution assay monitor (SAM) analyzes for ²³⁵U gamm-rays by using a high-efficiency germanium well detector. The detector`s high counting efficiency permits analysis of small samples (7 mL) from these dissolutions, and the counting geometry minimizes sample geometry uncertainties. Counting each sample for thirty minutes delivers excellent precision across the calibration range of 3 to 12 g uranium per liter. As shown by interlaboratory calibration, the gamma-ray spectrometer provides overall (counting, calibration, geometric,...) uncertainties less than 0.7% one sigma. Gamma-rays from a reference source, used to provide live-time corrections, are collimated to avoid absorption by the sample in the detector well. Since sample masses are small, minor self-attenuation corrections are calculated from chemical composition data rather than determined in separate transmission measurements. This avoids employing short-lived transmission sources for self-attenuation corrections.
Report Numbers
E 1.99:wsrc-ms--91-035
E 1.99: conf-910774--92
conf-910774--92
wsrc-ms--91-035
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
12/31/1991.
"wsrc-ms--91-035"
" conf-910774--92"
"DE92009629"
32. Institute of Nuclear Materials Management (INMM) annual meeting,New Orleans, LA (United States),28-31 Jul 1991.
Sigg, R.A.
Funding Information
AC09-89SR18035
View MARC record | catkey: 14661067