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Decontamination of radioactive effluent with clinoptilolite

Author: D W Rhodes; M W Wilding; National Reactor Testing Station, Idaho (U.S.); Phillips Petroleum Company. Atomic Energy Division.; Idaho Chemical Processing Plant.
Publisher: [Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1965.
Series: AEC research and development report.; U.S. Atomic Energy Commission.; Idaho Operations Office.; IDO; TID, 4500 42nd ed.
Edition/Format:   Print book : EnglishView all editions and formats
Database:WorldCat
Summary:
The removal of strontium-90 and cesium-137 from fuel storage basin effluent by ion exchange using the mineral clinoptilolite as the exchanger is described. The concentration of cesium-137 in the effluent after decontamination was less than its drinking water tolerance, and the concentration of strontium-90 was approximately equal to its tolerance.
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Additional Physical Format: Online version:
Rhodes, D.W. (Donald Walter), 1919-
Decontamination of radioactive effluent with clinoptilolite.
[Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1965
(OCoLC)727422500
Document Type: Book
All Authors / Contributors: D W Rhodes; M W Wilding; National Reactor Testing Station, Idaho (U.S.); Phillips Petroleum Company. Atomic Energy Division.; Idaho Chemical Processing Plant.
OCLC Number: 71086417
Notes: "Issued: July 1965."
"Waste Disposal and Processing ; TID-4500 (42nd Ed.)."
"National Reactor Testing Station"--Cover.
Description: 16 pages : illustrations ; 28 cm.
Series Title: AEC research and development report.; U.S. Atomic Energy Commission.; Idaho Operations Office.; IDO; TID, 4500 42nd ed.
Other Titles: Technical report archive and image library.
Responsibility: by D.W. Rhodes and M.W. Wilding.

Abstract:

The removal of strontium-90 and cesium-137 from fuel storage basin effluent by ion exchange using the mineral clinoptilolite as the exchanger is described. The concentration of cesium-137 in the effluent after decontamination was less than its drinking water tolerance, and the concentration of strontium-90 was approximately equal to its tolerance.

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