DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Investigation of residual anode material after electrorefining uranium in molten chloride salt

Authors:
; ;
Publication Date:
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
OSTI Identifier:
1252504
Grant/Contract Number:  
AC02-06CH11357
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Name: Journal of Nuclear Materials Journal Volume: 467 Journal Issue: P2; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Rose, M. A., Williamson, M. A., and Willit, J. Investigation of residual anode material after electrorefining uranium in molten chloride salt. Netherlands: N. p., 2015. Web. doi:10.1016/j.jnucmat.2015.10.015.
Rose, M. A., Williamson, M. A., & Willit, J. Investigation of residual anode material after electrorefining uranium in molten chloride salt. Netherlands. https://doi.org/10.1016/j.jnucmat.2015.10.015
Rose, M. A., Williamson, M. A., and Willit, J. Tue . "Investigation of residual anode material after electrorefining uranium in molten chloride salt". Netherlands. https://doi.org/10.1016/j.jnucmat.2015.10.015.
@article{osti_1252504,
title = {Investigation of residual anode material after electrorefining uranium in molten chloride salt},
author = {Rose, M. A. and Williamson, M. A. and Willit, J.},
abstractNote = {},
doi = {10.1016/j.jnucmat.2015.10.015},
journal = {Journal of Nuclear Materials},
number = P2,
volume = 467,
place = {Netherlands},
year = {Tue Dec 01 00:00:00 EST 2015},
month = {Tue Dec 01 00:00:00 EST 2015}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.jnucmat.2015.10.015

Citation Metrics:
Cited by: 3 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

Behavior of U-Zr Alloy Containing Simulated Fission Products during Anodic Dissolution in Molten Chloride Electrolyte
journal, March 2010

  • Iizuka, Masatoshi; Omori, Takashi; Tsukada, Takeshi
  • Journal of Nuclear Science and Technology, Vol. 47, Issue 3
  • DOI: 10.1080/18811248.2010.9711951

Determining the Exchange Current Density and Tafel Constant for Uranium in LiCl/KCl Eutectic
journal, October 2014

  • Rose, M. A.; Williamson, M. A.; Willit, J.
  • ECS Electrochemistry Letters, Vol. 4, Issue 1
  • DOI: 10.1149/2.0101501eel

Modeling of anodic dissolution of U–Pu–Zr ternary alloy in the molten LiCl–KCl electrolyte
journal, February 2005

  • Iizuka, Masatoshi; Kinoshita, Kensuke; Koyama, Tadafumi
  • Journal of Physics and Chemistry of Solids, Vol. 66, Issue 2-4
  • DOI: 10.1016/j.jpcs.2004.06.055

Development of Treatment Process for Anode Residue from Molten Salt Electrorefining of Spent Metallic Fast Reactor Fuel
journal, March 2013

  • Iizuka, Masatoshi; Akagi, Masaaki; Omori, Takashi
  • Nuclear Technology, Vol. 181, Issue 3
  • DOI: 10.13182/NT13-A15807

Experimental investigations and thermodynamic modelling of KCl–LiCl–UCl3 system
journal, June 2014


Investigation of a LiCl–KCl–UCl3 system using a combination of X-ray diffraction and differential thermal analyses
journal, October 2013