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Title: Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions

Abstract

The feasibility of a highly concentrated uranyl nitrate target for 99Mo production and recovery was investigated with respect to three separate resins. Two resins were inorganic-based – titania and zirconia – and the other was organic-based utilizing Aliquot® 336 extraction chromatography. Results show that pH has a significant effect on select fission products such as Zr whereas Mo is reasonably well retained between pH 0 and 2. Temperature also appreciably affected the retention of Mo. Using a normal-phase titania resin (Sachtapore®), the sorption of Mo was investigated by varying acid and uranium concentrations. The stability of the resin was also studied as a function of acid concentration. Results from the batch studies were then input into the in-house Versatile Reaction Separation (VERSE) code in order to design and optimize a recovery column for 99Mo. The experimental and model results show that >99.9% of the 99Mo can be recovered in the presence of saturated uranyl nitrate solutions.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (NA-23)
OSTI Identifier:
1570300
Report Number(s):
ANL/CFCT-19/19
156461
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Brown, M. Alex, McLain, Derek R., Copple, Jacqueline M., Jerden, James L., Youker, Amanda, and Tkac, Peter. Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions. United States: N. p., 2019. Web. doi:10.2172/1570300.
Brown, M. Alex, McLain, Derek R., Copple, Jacqueline M., Jerden, James L., Youker, Amanda, & Tkac, Peter. Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions. United States. doi:10.2172/1570300.
Brown, M. Alex, McLain, Derek R., Copple, Jacqueline M., Jerden, James L., Youker, Amanda, and Tkac, Peter. Tue . "Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions". United States. doi:10.2172/1570300. https://www.osti.gov/servlets/purl/1570300.
@article{osti_1570300,
title = {Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions},
author = {Brown, M. Alex and McLain, Derek R. and Copple, Jacqueline M. and Jerden, James L. and Youker, Amanda and Tkac, Peter},
abstractNote = {The feasibility of a highly concentrated uranyl nitrate target for 99Mo production and recovery was investigated with respect to three separate resins. Two resins were inorganic-based – titania and zirconia – and the other was organic-based utilizing Aliquot® 336 extraction chromatography. Results show that pH has a significant effect on select fission products such as Zr whereas Mo is reasonably well retained between pH 0 and 2. Temperature also appreciably affected the retention of Mo. Using a normal-phase titania resin (Sachtapore®), the sorption of Mo was investigated by varying acid and uranium concentrations. The stability of the resin was also studied as a function of acid concentration. Results from the batch studies were then input into the in-house Versatile Reaction Separation (VERSE) code in order to design and optimize a recovery column for 99Mo. The experimental and model results show that >99.9% of the 99Mo can be recovered in the presence of saturated uranyl nitrate solutions.},
doi = {10.2172/1570300},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

Technical Report:

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