Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes [electronic resource].

Published:: Richland, Wash. : Pacific Northwest Laboratory, 1984.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators:: Pacific Northwest Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

A passive neutron monitor has been designed and built for determining the residual transuranic (TRU) and plutonium content of chopped leached fuel hulls and other solid wastes from spent Fast Flux Test Facility (FFTF) fuel. The system was designed to measure as little as 8 g of plutonium or 88 mg of TRU in a waste package as large as a 208-l drum which could be emitting up to 220,000 R/hr of gamma radiation. For practical purposes, maximum assay times were chosen to be 10,000 sec. The monitor consists of 96 /sup 10/BF/sub 3/ neutron sensitive proportional counting tubes each 5.08 cm in diameter and 183 cm in active length. Tables of neutron emission rates from both spontaneous fission and (..cap alpha..,n) reactions on oxygen are given for all contributing isotopes expected to be present in spent FFTF fuel. Tables of neutron yeilds from isotopic compositions predicted for various exposures and cooling times are also given. Methods of data reduction and sources, magnitude, and control of errors are discussed. Backgrounds and efficiencies have been measured and are reported. A section describing step-by-step operational procedures is included. Guidelines and procedures for quality control and troubleshooting are also given. 13 references, 15 figures, 4 tables.

Report Numbers:

E 1.99:pnl-4966
pnl-4966

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Note:

Published through SciTech Connect.
02/01/1984.
"pnl-4966"
"DE84006676"
Brown, D.P.; Rieck, H.G. Jr.; Brodzinski, R.L.; Rogers, L.A.

Funding Information:

AC06-76RL01830

View MARC record | catkey: 14371667