Actions for Characterization of decommissioned reactor internals [electronic resource] : Direct-assay method assessment

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Characterization of decommissioned reactor internals [electronic resource] : Direct-assay method assessment

Published
Washington, D.C. : United States. Dept. of Energy, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
53 pages : digital, PDF file
Additional Creators
United States. Department of Energy and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
This study describes the direct-assay technique for measuring activation levels of irradiated reactor component hardware. It also compares the direct-assay technique with calculational analysis methods that predict activation levels. Direct assay is performed in four steps: (a) planning and component selection, (b) onsite measurements, (c) radiochemical analysis, and (d) data analysis and classification. Uncertainties are estimated for each step of this process, and an overall uncertainty in the classification accuracy is calculated as about ±35%. Numerous research ideas are identified to help reduce the uncertainty level; many of these ideas would improve activation determinations performed by either direct assay or by calculational analysis methods.
Report Numbers
E 1.99:doe/llw--161
doe/llw--161
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
03/01/1993.
"doe/llw--161"
"DE93013739"
Cline, J.E.
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Cline (J.E.) and Associates, Inc., Rockville, MD (United States)
Type of Report and Period Covered Note
Topical; 03/01/1993 - 03/01/1993
Funding Information
AC07-76ID01570
View MARC record | catkey: 13802930