Characterization of radiolytically generated degradation products in the strip section of a TRUEX flowsheet

Peterman, Dean R. ; Olson, Lonnie G. ; Groenewold, Gary S. ; McDowell, Rocklan G. ; Tillotson, Richard D. ; Law, Jack D.

Idaho National Laboratory

关键词: Degradation;    Radiolysis;    Truex;    38 Radiation Chemistry, Radiochemistry, And Nuclear Chemistry Degradation;   

DOI  :  10.2172/1122116
RP-ID  :  INL/EXT-13-29727
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1122116

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report presents a summary of the work performed to meet the FCRD level 2 milestone M3FT-13IN0302053, “Identification of TRUEX Strip Degradation.” The INL radiolysis test loop has been used to identify radiolytically generated degradation products in the strip section of the TRUEX flowsheet. These data were used to evaluate impact of the formation of radiolytic degradation products in the strip section upon the efficacy of the TRUEX flowsheet for the recovery of trivalent actinides and lanthanides from acidic solution. The nominal composition of the TRUEX solvent used in this study is 0.2 M CMPO and 1.4 M TBP dissolved in n-dodecane and the nominal composition of the TRUEX strip solution is 1.5 M lactic acid and 0.050 M diethylenetriaminepentaacetic acid. Gamma irradiation of a mixture of TRUEX process solvent and stripping solution in the test loop does not adversely impact flowsheet performance as measured by stripping americium ratios. The observed increase in americium stripping distribution ratios with increasing absorbed dose indicates the radiolytic production of organic soluble degradation compounds.