Published February 24, 1989 | Version v1
Report Restricted

Ion chromatographic separation of radiostrontium from nuclear fuel reprocessing solutions of high ionic strength

  • 1. Brigham Young Univ., Provo, UT (United States). Dept. of Chemistry
  • 2. Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)

Description

Determination of 90Sr in nuclear fuel reprocessing solutions can be facilitated by a preparatory separation using analytical ion chromatography (IC). Furthermore, a novel acid suppression system is described which permits IC separation even in the presence of very strong (0.33 M) acid. Following acid suppression (where needed), Sr2+ is concentrated and separated from most other solution components by selective adsorption on cation concentrator columns. Cation species retained on the concentrator columns with strontium are subsequently separated on a cation IC column. The Sr2+ peak aliquot is collected for subsequent radiostrontium analysis by liquid scintillation counting of the beta activity. Results have shown quantitative separation and recovery of strontium. The entire separation system is automated under computer control and is able to handle samples of large (500 mi) and small (uL) sizes

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92017382; NTIS; INIS; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
27 p.
Report number
WINCO--11501

Optional Information

Contract/Grant/Project number
Contract AC07-84ID12435
Funding organization
USDOE, Washington, DC (United States).