Am(VI) Radiolysis

Mincher, Bruce J.; Grimes, Travis S.

doi:10.2172/1466814

Title: Am(VI) Radiolysis

Full Record
Other Related Research

Abstract

This report summarizes activities related to measuring hexavalent Am stability under irradiation conditions for FY17, in completion of FCR&D Milestone M3FT-17IN030103022. The rate at which Am(VI) reduced and Am(V) grew in when exposed to γ-irradiation was measured by UV/Vis spectroscopy in different [HNO₃] and for different total [Am]. These rates were then compared to similar experiments with the added fuel dissolution constituents Ce, U and Zr. Cerium provided radio-protection for Am(VI), U appears to have conferred slight radioprotection, while Zr had no such effect.

Authors:

Mincher, Bruce J. ^[1]; Grimes, Travis S. ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Fri Sep 15 00:00:00 EDT 2017

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1466814

Report Number(s):: INL/EXT-17-43355

DOE Contract Number:: AC07-05ID14517

Resource Type:: Technical Report

Country of Publication:: United Kingdom

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; americium, fuel cycle, oxidation, partitioning, ruthenium, solvent extraction

Citation Formats


                    Mincher, Bruce J., and Grimes, Travis S. Am(VI) Radiolysis.  United Kingdom: N. p., 2017. 
        Web.  doi:10.2172/1466814.

Copy to clipboard


                    Mincher, Bruce J., & Grimes, Travis S. Am(VI) Radiolysis.  United Kingdom.  https://doi.org/10.2172/1466814

Copy to clipboard


                    Mincher, Bruce J., and Grimes, Travis S. 2017.  
        "Am(VI) Radiolysis".  United Kingdom.  https://doi.org/10.2172/1466814.  https://www.osti.gov/servlets/purl/1466814.

Copy to clipboard


                    
@article{osti_1466814,

  title        = {Am(VI) Radiolysis},

  author       = {Mincher, Bruce J. and Grimes, Travis S.},

  abstractNote = {This report summarizes activities related to measuring hexavalent Am stability under irradiation conditions for FY17, in completion of FCR&D Milestone M3FT-17IN030103022. The rate at which Am(VI) reduced and Am(V) grew in when exposed to γ-irradiation was measured by UV/Vis spectroscopy in different [HNO3] and for different total [Am]. These rates were then compared to similar experiments with the added fuel dissolution constituents Ce, U and Zr. Cerium provided radio-protection for Am(VI), U appears to have conferred slight radioprotection, while Zr had no such effect.},

  doi          = {10.2172/1466814},

  url          = {https://www.osti.gov/biblio/1466814},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United Kingdom},

  year         = {Fri Sep 15 00:00:00 EDT 2017},

  month        = {Fri Sep 15 00:00:00 EDT 2017}

}

Copy to clipboard

Technical Report:

View Technical Report

https://doi.org/10.2172/1466814

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Am(VI) Extraction Final Report: FY16

Technical Report Mincher, Bruce; Grimes, Travis; Tillotson, Richard; ...

This report summarizes activities related to hexavalent Am extraction for FY16, in completion of FCR&D Milestone M3FT-16IN030103027. Activities concentrated on three areas of research: 1) centrifugal contactor hot testing, 2) Am(VI) stability studies, and 3) alternative oxidant studies. A brief summary of each task follows. Hot Testing: A new engineering-scale oxidation and solvent extraction test bed was built at Idaho National Laboratory to allow for solvent extraction testing of minor actinide separation concepts. The test bed consists of an oxidation vessel, filtration apparatus, four, 3D printed, 2-cm diameter centrifugal contactors, feed/product vessels, and sample ports. This system replaced the previousmore »« less
https://doi.org/10.2172/1364484

Full Text Available
Am(VI) Extraction Final Report: FY17

Technical Report Mincher, Bruce; Grimes, Travis; Schmitt, Nicholas; ...

This report summarizes activities related to hexavalent Am extraction for FY17, in completion of FCR&D Milestone M4FT-16IN0301030211. Activities concentrated on three areas of research: 1) centrifugal contactor hot testing, 2) Am(VI) stability studies, and 3) batch contact solvent extraction experiments related to ruthenium interference in Am oxidation and re-oxidation of previously contacted aqueous phases. Each of these tasks has already been, or will be discussed in detail in its own milestone report, therefore, only a brief summary of each task follows in this report.
https://doi.org/10.2172/1408743

Full Text Available
Recovery of Oxidized Actinides, Np(VI), Pu(VI), and Am(VI), from Cocrystallized Uranyl Nitrate Hexahydrate: A Single Technology Approach to Used Nuclear Fuel Recycling

Journal Article Einkauf, Jeffrey; Burns, Jonathan - Industrial and Engineering Chemistry Research

In this work, the utility of recovering cocrystallized Np, Pu, and Am from a uranyl nitrate hexahydrate crystalline phase has been examined. Progressive dissolution studies were carried out on samples of either Np(VI), Pu(VI), or Am(VI) cocrystallized with uranyl nitrate hexahydrate, resulting in a linear relationship between the amount of actinides dissolved as a function of volume of HNO₃ added, which indicates homogeneous distribution of the transuranic species throughout the crystalline solid. The ratio of the concentration of U to the heavier actinides was maintained over the entire dissolution and mimicked that of the starting cocrystallization solution. A series ofmore »« less
https://doi.org/10.1021/acs.iecr.0c00381

Full Text Available
SPECTROCHEMICAL ANALYSIS OF 'FISSIUM' FOR CERIUM AND LANTHANUM

Journal Article Boyes, Jr, G; Ramsay, J; Phelps, R - Talanta (England)

"Fissium" is a synthetic spent plutonium-rich reactor fuel which has a nominal wt.% composition of 2.5 Fe, 0.7 Ce, 1.3 La, 0.7 Mo, 1.3 Ru, and 0.8 Zr. It is used as a stand-in for irradiated fuel in the study of pyrometallurgical methods of treatment for the removal of fission products. To evaluate the cesium and lanthanum contents of the fuel alloy, as well as the by-products of this treatment, a spectrochemical method was developed which has a coefficient of variation of 6% and comparable accuracy when amounts ranging from 40 to 200 - g are determined. The recommended proceduremore »« less
https://doi.org/10.1016/0039-9140(60)80270-6
Hydrolysis and Radiation Chemistry of the DGAs

Technical Report Mincher, Bruce; Zarzana, Christopher

This document was prepared to meet FCR&D level 3 milestone M3FT-16IN030104052, “continue the study of the short chain compounds,” and, “ study the radiolysis of the non-symmetrical DGA (D3DODGA)….,” under the Radiation Chemistry FCR&D work package. Toward these goals, the short chain DGA, tetraethyldiglycolamide (TEDGA) was investigated for its hydrolytic stability in HNO3 solution, with comparisons to the less oxidizing mineral acid HCl. Initial gamma-irradiations were also performed on DGA solutions, to inform a more detailed investigation of several short chain compounds anticipated for FY17. The hydrolytic and radiolysis behavior of TEDGA is of interest for two reasons. First, previousmore »« less
https://doi.org/10.2172/1406975

Full Text Available

Similar Records