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Main Title An investigation of airborne radioactive effluent from an operating nuclear fuel reprocessing plant /
Author Cochra, J. A. ; Smit, D. G. ; Magn, P. J. ; Shleie, B. ;
Other Authors
Author Title of a Work
Cochran, Joseph A.
Cochran, J. A.
CORP Author Northeastern Radiological Health Laboratory, Winchester, Mass.
Publisher U.S. Dept. of Health, Education, and Welfare, Public Health Service, Environmental Health Service, Bureau of Radiological Health,
Year Published 1970
Report Number BRH/NERHL-70-3;
Stock Number PB-193 803
OCLC Number 20062815
Subjects Radioactive pollution of the atmosphere--Measurement. ; Reactor fuel reprocessing. ; Air Pollution, Radioactive--prevention & control. ; Waste Disposal, Fluid. ; Nuclear Power Plants. ; Massachusetts.
Additional Subjects ( Nuclear fuel reprocessing ; Air pollution) ; ( Radioactive contaminants ; Nuclear fuel reprocessing) ; Effluents ; Chimneys ; Sampling ; Geiger counters ; Radiation dosage ; Populations ; Environments ; Samplers ; Nuclear fuel reprocessing plants
Library Call Number Additional Info Location Last
EKBD  BRH/NERHL 70-3 Research Triangle Park Library/RTP, NC 08/29/2017
NTIS  PB-193 803 Some EPA libraries have a fiche copy filed under the call number shown. 07/26/2022
Collation x, 39 pages : illustrations ; 27 cm.
This paper describes studies carried out at an operating nuclear fuel reprocessing plant for the purposes of characterizing the stack effluent, measuring the environmental levels of activity due to components of stack release, and evaluating instrumentation and methodology used to sample both at the stack and in the environment. Four field sampling stations, located in the vicinity of the plant perimeter, and a stack sampler simultaneously monitored 85Kr, 129I, and 3H (gaseous and water vapor) during two dissolution cycles. Particulates were monitored at the stack and one field station. Measurements are presented and discussed in terms of emission level versus specific plant operations, primarily the dissolution cycle. The instrumentation used in this study includes thin-window geiger detectors and flow-through ionization chambers for 85Kr; bubblers, traps, and grab samplers for 3H; and resin traps for 129I. Choice of methodology and instrumentation is discussed with emphasis placed on a system usable in determining dose to a population in the plant vicinity. (Author)
"July 1970." Includes bibliographical references.