Nondestructive assay system for use in decommissioning a plutonium-handling facility [electronic resource].

Published: Argonne, Ill. : Argonne National Laboratory, 1979.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: Pages: 30 : digital, PDF file
Additional Creators: Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

Argonne National Laboratory is decommissioning a facility used to fabricate reactor fuel elements. The equipment is contaminated with alpha emitters at levels up to 10/sup 12/ dpm/100 cm/sup 2/. The objective of decontamination is to reduce the TRU concentrations below 10 nCi/g of waste. A portable NDA procedure using NaI(T1) gamma-spectrometric techniques was selected to measure the residual Pu and /sup 241/Am in the glove boxes. Assays were performed at different stages in the decontamination process to estimate the detection system sensitivity and the effectiveness of the cleaning efforts.

Report Numbers

E 1.99:anl-79-60
anl-79-60

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Note

Published through SciTech Connect.
07/01/1979.
"anl-79-60"
Perry, R.B.; Roche, C.T.; Vronich, J.J.; Bellinger, F.O.

Funding Information

W-31-109-ENG-38

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