TRUEX Radiolysis Testing Using the INL Radiolysis Test Loop: FY-2012 Status Report
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
The INL radiolysis test loop has been used to evaluate the affect of radiolytic degradation upon the efficacy of the strip section 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.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1076536
- Report Number(s):
- INL/EXT--12-27285
- Country of Publication:
- United States
- Language:
- English
Similar Records
Characterization of radiolytically generated degradation products in the strip section of a TRUEX flowsheet
Summary of TRUEX Radiolysis Testing Using the INL Radiolysis Test Loop
Extraction and recovery of plutonium and americium from nitric acid waste solutions by the TRUEX process - continuing development studies
Technical Report
·
Thu Aug 01 00:00:00 EDT 2013
·
OSTI ID:1122116
Summary of TRUEX Radiolysis Testing Using the INL Radiolysis Test Loop
Technical Report
·
Wed Feb 29 19:00:00 EST 2012
·
OSTI ID:1046071
Extraction and recovery of plutonium and americium from nitric acid waste solutions by the TRUEX process - continuing development studies
Technical Report
·
Sun Sep 01 00:00:00 EDT 1985
·
OSTI ID:5160292