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Title: Compositions and methods for treating nuclear fuel

Abstract

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

Inventors:
; ; ; ; ;
Publication Date:
Research Org.:
PNNL (Pacific Northwest National Laboratory (PNNL), Richland, WA (United States))
Sponsoring Org.:
USDOE
OSTI Identifier:
1118256
Patent Number(s):
8,636,966
Application Number:
13/964,914
Assignee:
Battelle Memorial Institute (Richland, WA)
DOE Contract Number:  
AC05-76RLO1830
Resource Type:
Patent
Resource Relation:
Patent File Date: 2013 Aug 12
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, and Peper, Shane M. Compositions and methods for treating nuclear fuel. United States: N. p., 2014. Web.
Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, & Peper, Shane M. Compositions and methods for treating nuclear fuel. United States.
Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, and Peper, Shane M. Tue . "Compositions and methods for treating nuclear fuel". United States. https://www.osti.gov/servlets/purl/1118256.
@article{osti_1118256,
title = {Compositions and methods for treating nuclear fuel},
author = {Soderquist, Chuck Z and Johnsen, Amanda M and McNamara, Bruce K and Hanson, Brady D and Smith, Steven C and Peper, Shane M},
abstractNote = {Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2014},
month = {1}
}

Patent:

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Works referenced in this record:

Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues
journal, November 1990


New Approach to the Nuclear Fuel Reprocessing in Non-acidic Aqueous Solutions
journal, October 2001

  • Asanuma, Noriko; Harada, Masayuki; Ikeda, Yasuhisa
  • Journal of Nuclear Science and Technology, Vol. 38, Issue 10
  • DOI: 10.1080/18811248.2001.9715107

Formation of the ammonium-uranyl-carbonate complexes of the type (NH4)4[UO2(CO3)3], prepared by precipitative re-extraction
journal, January 1984


Metallic fission-product inclusions in irradiated oxide fuels
journal, February 1968


Precipitation studies of ammonium uranyl carbonate from UO2F2 solutions
journal, May 1989

  • Kan-Sen, Chou; Ding-Yi, Lin; Mu-Chang, Shieh
  • Journal of Nuclear Materials, Vol. 165, Issue 2, p. 171-178
  • DOI: 10.1016/0022-3115(89)90246-8

Formation of Studtite during the Oxidative Dissolution of UO 2 by Hydrogen Peroxide:  A SFM Study
journal, December 2004

  • Clarens, F.; de Pablo, J.; Díez-Pérez, I.
  • Environmental Science & Technology, Vol. 38, Issue 24
  • DOI: 10.1021/es0492891

The chemical effects of composition changes in irradiated oxide fuel materials
journal, November 1971


The oxidative dissolution mechanism of uranium dioxide. I. The effect of temperature in hydrogen carbonate medium
journal, October 1999

  • Pablo, Joan de; Casas, Ignasi; Giménez, Javier
  • Geochimica et Cosmochimica Acta, Vol. 63, Issue 19-20, p. 3097-3103
  • DOI: 10.1016/S0016-7037(99)00237-9

Evaluation of Process That Might Lead to Separation of Actinides in Waste Storage Tanks Under Alkaline Conditions
journal, January 2000

  • Del Cul, G. D.; Toth, L. M.; Bond, W. D.
  • Separation Science and Technology, Vol. 35, Issue 13
  • DOI: 10.1081/SS-100102093

Surface electrochemistry of UO2 in dilute alkaline hydrogen peroxide solutions: Part II. Effects of carbonate ions
journal, April 2006


The alizarin-S spot test for aluminium in the presence of zirconium, in systematic qualitative analysis
journal, September 1964

  • Griepink, B. F. A.; Veldman, Judith
  • Mikrochimica Acta, Vol. 52, Issue 5
  • DOI: 10.1007/BF01215722

Recovery of Uranium from Ammonium Uranyl Carbonate (AUC) Effluents by Combined Ion Exchange and Membrane Separation
journal, January 2005

  • Gureli, Lutfiye; Apak, Resat
  • Separation Science and Technology, Vol. 39, Issue 8
  • DOI: 10.1081/SS-120030793

Microanalysis of inclusions in irradiated UO2
journal, April 1967


Study on Electrolytic Recoveries of Carbonate Salt and Uranium from a Uranyl Peroxo Carbonato Complex Solution Generated from a Carbonate-Leaching Process
journal, February 2009

  • Kim, Kwang-Wook; Kim, Yeon-Hwa; Lee, Se-Yoon
  • Industrial & Engineering Chemistry Research, Vol. 48, Issue 4
  • DOI: 10.1021/ie800990r

X-ray diffraction studies on irradiated nuclear fuels
journal, May 1984


The chemical state of the fission products in oxide fuels
journal, April 1985


Uranium recovery from industrial effluent by ion exchange—column experiments
journal, November 2005


Conversion of UF6 to UO2: A quasi-optimization of the ammonium uranyl carbonate process
journal, November 1991


On the dependence of characteristics of powders on the AUC process parameters
journal, February 1991

  • Marajofsky, A.; Perez, Lidia; Celora, Julia
  • Journal of Nuclear Materials, Vol. 178, Issue 2-3, p. 143-151
  • DOI: 10.1016/0022-3115(91)90379-L

Preparation and properties of complex carbonates of hexavalent actinides
journal, May 1983


Carbonate Leaching of Uranium from Contaminated Soils
journal, October 1997

  • Mason, C. F. V.; Turney, W. R. J. R.; Thomson, B. M.
  • Environmental Science & Technology, Vol. 31, Issue 10
  • DOI: 10.1021/es960843j

UO2 dissolution in the presence of hydrogen peroxide at pH>11
journal, January 2008

  • Meca, Sandra; Marti, Vincenc; de Pablo, Joan
  • Radiochimica Acta, Vol. 96, Issue 9-11
  • DOI: 10.1524/ract.2008.1534

Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-II
journal, June 1970


Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux
journal, January 1969


The conversion of UO2 via ammonium uranyl carbonate: Study of precipitation, chemical variation and powder properties
journal, September 1981


Kinetic Study of the Oxidative Dissolution of UO 2 in Aqueous Carbonate Media
journal, December 2004

  • Peper, Shane M.; Brodnax, Lia F.; Field, Stephanie E.
  • Industrial & Engineering Chemistry Research, Vol. 43, Issue 26
  • DOI: 10.1021/ie049457y

Experimental determination of UO2(cr) dissolution kinetics: Effects of solution saturation state and pH
journal, October 2005


Fuel corrosion processes under waste disposal conditions
journal, November 2000


Dissolution of spent nuclear fuel in carbonate–peroxide solution
journal, January 2010


Corrosion of uranium dioxide in hydrogen peroxide solutions
journal, May 2004


The isolation of 99Mo from fission material for use in the 99Mo/99mTc generator for medical use
journal, January 2004