RAPID ASSESSMENT OF 235U FROM URANIUM FUEL FABRICATION FACILITIES

Publication Date

1973-01-01

Volume

1

Issue

4

Start Page

9

Author(s)

W.F. Heine - North American Rockwell Corporation

J. D. Moore - North American Rockwell Corporation

File Attachment

V-1_4.pdf2.04 MB

Abstract

A method has been developed which permits rapid assessment of ²³⁵U in effluents from uranium fuel fabrication facilities. Gross alpha activity is used as a basis for determining precisely the ²³⁵u content in effluents containing uranium of known enrichment and for estimating ²³⁵u content in effluents containing uranium of unknown enrichment.