Actions for Monte Carlo calculational design of an NDA instrument for the assay of waste products from high enriched uranium spent fuels [electronic resource].

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Monte Carlo calculational design of an NDA instrument for the assay of waste products from high enriched uranium spent fuels [electronic resource].

Published
Los Alamos, N.M. : Los Alamos Scientific Laboratory, 1979.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 25 : digital, PDF file
Additional Creators
Los Alamos Scientific Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of /sup 235/U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 10/sup 6/ n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg /sup 252/Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of /sup 235/U is achievable with an end-of-life (1 mg) /sup 252/Cf source and a background rate of 0.5 x 10/sup 6/ n/s.
Report Numbers
E 1.99:la-ur-79-3218
E 1.99: conf-791117-4
conf-791117-4
la-ur-79-3218
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Note
Published through SciTech Connect.
01/01/1979.
"la-ur-79-3218"
" conf-791117-4"
ANS topical conference, Kiawah Island, SC, USA, 26 Nov 1979.
MacDonald, J.L.; Eccleston, G.W.; Cverna, F.H.; Schrandt, R.G.
Funding Information
W-7405-ENG-36
View MARC record | catkey: 14398345