Achieving Higher Accuracy in the Gamma-Ray Spectrocopic Assay of Holdup
Abstract
Gamma-ray spectroscopy is an important technique for the measurement of quantities of nuclear material holdup in processing equipment. Because the equipment in large facilities dedicated to uranium isotopic enrichment, uranium/plutonium scrap recovery or various stages of fuel fabrication is extensive, the total holdup may be large by its distribution alone, even if deposit thicknesses are small. Good accountability practices require unbiased measurements with uncertainties that are as small as possible. This paper describes new procedures for use with traditional holdup analysis methods based on gamma-ray spectroscopy. The procedures address the two sources of bias inherent in traditional gamma-ray measurements of holdup. Holdup measurements are performed with collimated, shielded gamma-ray detectors. The measurement distance is chosen to simplify the deposit geometry to that of a point, line or area. The quantitative holdup result is based on the net count rate of a representative gamma ray. This rate is corrected for contributions from room background and for attenuation by the process equipment. Traditional holdup measurements assume that the width of the point or line deposit is very small compared to the measurement distance, and that the self-attenuation effects can be neglected. Because each point or line deposit has a finite width andmore »
- Authors:
- Publication Date:
- Research Org.:
- Los Alamos National Lab., NM (US)
- Sponsoring Org.:
- USDOE Office of Nonproliferation and National Security (NN) (US)
- OSTI Identifier:
- 775830
- Report Number(s):
- LA-13699-MS
TRN: US0101346
- DOE Contract Number:
- W-7405-ENG-36
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: 1 Sep 2000
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACCURACY; ALGORITHMS; ATTENUATION; GAMMA SPECTROSCOPY; URANIUM; PLUTONIUM; MATERIAL UNACCOUNTED FOR
Citation Formats
Russo, P A, Wenz, T R, Smith, S E, and Harris, J F. Achieving Higher Accuracy in the Gamma-Ray Spectrocopic Assay of Holdup. United States: N. p., 2000.
Web. doi:10.2172/775830.
Russo, P A, Wenz, T R, Smith, S E, & Harris, J F. Achieving Higher Accuracy in the Gamma-Ray Spectrocopic Assay of Holdup. United States. https://doi.org/10.2172/775830
Russo, P A, Wenz, T R, Smith, S E, and Harris, J F. Fri .
"Achieving Higher Accuracy in the Gamma-Ray Spectrocopic Assay of Holdup". United States. https://doi.org/10.2172/775830. https://www.osti.gov/servlets/purl/775830.
@article{osti_775830,
title = {Achieving Higher Accuracy in the Gamma-Ray Spectrocopic Assay of Holdup},
author = {Russo, P A and Wenz, T R and Smith, S E and Harris, J F},
abstractNote = {Gamma-ray spectroscopy is an important technique for the measurement of quantities of nuclear material holdup in processing equipment. Because the equipment in large facilities dedicated to uranium isotopic enrichment, uranium/plutonium scrap recovery or various stages of fuel fabrication is extensive, the total holdup may be large by its distribution alone, even if deposit thicknesses are small. Good accountability practices require unbiased measurements with uncertainties that are as small as possible. This paper describes new procedures for use with traditional holdup analysis methods based on gamma-ray spectroscopy. The procedures address the two sources of bias inherent in traditional gamma-ray measurements of holdup. Holdup measurements are performed with collimated, shielded gamma-ray detectors. The measurement distance is chosen to simplify the deposit geometry to that of a point, line or area. The quantitative holdup result is based on the net count rate of a representative gamma ray. This rate is corrected for contributions from room background and for attenuation by the process equipment. Traditional holdup measurements assume that the width of the point or line deposit is very small compared to the measurement distance, and that the self-attenuation effects can be neglected. Because each point or line deposit has a finite width and because self-attenuation affects all measurements, bias is incurred in both assumptions. In both cases the bias is negative, explaining the systematically low results of gamma-ray holdup measurements. The new procedures correct for bias that arises from both the finite-source effects and the gamma-ray self-attenuation. The procedures used to correct for both of these effects apply to the generalized geometries. One common empirical parameter is used for both corrections. It self-consistently limits the total error incurred (from uncertain knowledge of this parameter) in the combined correction process, so that it is compelling to use these procedures. The algorithms and the procedures are simple, general, and easily automated for use plant-wide. This paper shows the derivation of the new, generalized correction algorithms for finite-source and self-attenuation effects. It also presents an analysis of the sensitivity of the holdup result to the uncertainty in the empirical parameter when one or both corrections are made. The paper uses specific examples of the magnitudes of finite-source and self-attenuation corrections to measurements that were made in the field. It discusses the automated implementation of the correction procedure.},
doi = {10.2172/775830},
url = {https://www.osti.gov/biblio/775830},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {9}
}