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Title: Recovery of Mo in LEU-Modified Cintichem Process at Elevated Mo Concentrations

Abstract

Argonne National Laboratory with support from DOE’s National Nuclear Security Administration Office of Material Management & Minimization (M3) is helping SHINE Medical Technologies in developing domestic production of Mo-99. SHINE is planning to produce Mo-99 by fission of low enriched uranium-235 (LEU) in a subcritical aqueous solution using accelerator-based neutron generation.1 SHINE’s subcritical system can contain ~250L of LEU solution that is processed through a recovery titania-based column to recover Mo, while the remaining LEU solution can be available for another irradiation. The Mo-containing solution is then fed into another titania-based concentration column to further concentrate the solution to allow for the final purification step using the LEU modified Cintichem (LMC) process. The LMC process is a relatively small-scale process that was designed to work with 50mL volumes. By concentrating the Mo solution that feeds into the LMC process from ~250L to ~50mL, the actual chemical concentration of Mo becomes important. It is estimated that up to ~15mM Mo concentration could be present in the LMC feed. Since the LMC process was originally proposed for purification of Mo after dissolution of irradiated U solid targets, the chemical concentration of Mo was not a concern, due to presence of only tracemore » amounts of Mo.« less

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 (M3)
OSTI Identifier:
1570469
Report Number(s):
ANL/CFCT-19/15
156575
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Bettinardi, David J., and Tkac, Peter. Recovery of Mo in LEU-Modified Cintichem Process at Elevated Mo Concentrations. United States: N. p., 2019. Web. doi:10.2172/1570469.
Bettinardi, David J., & Tkac, Peter. Recovery of Mo in LEU-Modified Cintichem Process at Elevated Mo Concentrations. United States. doi:10.2172/1570469.
Bettinardi, David J., and Tkac, Peter. Sun . "Recovery of Mo in LEU-Modified Cintichem Process at Elevated Mo Concentrations". United States. doi:10.2172/1570469. https://www.osti.gov/servlets/purl/1570469.
@article{osti_1570469,
title = {Recovery of Mo in LEU-Modified Cintichem Process at Elevated Mo Concentrations},
author = {Bettinardi, David J. and Tkac, Peter},
abstractNote = {Argonne National Laboratory with support from DOE’s National Nuclear Security Administration Office of Material Management & Minimization (M3) is helping SHINE Medical Technologies in developing domestic production of Mo-99. SHINE is planning to produce Mo-99 by fission of low enriched uranium-235 (LEU) in a subcritical aqueous solution using accelerator-based neutron generation.1 SHINE’s subcritical system can contain ~250L of LEU solution that is processed through a recovery titania-based column to recover Mo, while the remaining LEU solution can be available for another irradiation. The Mo-containing solution is then fed into another titania-based concentration column to further concentrate the solution to allow for the final purification step using the LEU modified Cintichem (LMC) process. The LMC process is a relatively small-scale process that was designed to work with 50mL volumes. By concentrating the Mo solution that feeds into the LMC process from ~250L to ~50mL, the actual chemical concentration of Mo becomes important. It is estimated that up to ~15mM Mo concentration could be present in the LMC feed. Since the LMC process was originally proposed for purification of Mo after dissolution of irradiated U solid targets, the chemical concentration of Mo was not a concern, due to presence of only trace amounts of Mo.},
doi = {10.2172/1570469},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

Technical Report:

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