Distribution of Fission Products into Tributyl Phosphate under Applied Nuclear Fuel Recycling Conditions

被引:29
|
作者
Baldwin, Anna G. [1 ]
Bridges, Nicholas J. [2 ]
Braley, Jenifer C. [1 ]
机构
[1] Colorado Sch Mines, Golden, CO 80401 USA
[2] Savannah River Natl Lab, Aiken, SC 29808 USA
关键词
NORMAL-BUTYL PHOSPHATE; EXTRACTING SOLVENT; INORGANIC NITRATES; ZIRCONIUM NITRATE; 3RD PHASE; TBP; CHEMISTRY; SYSTEM; DILUENT; THORIUM;
D O I
10.1021/acs.iecr.6b04056
中图分类号
TQ [化学工业];
学科分类号
0817 ;
摘要
Tributyl phosphate (TBP) is an important industrial extractant used in the Plutonium Uranium Redox Extraction (PUREX) process for recovering uranium and plutonium from used nuclear fuel. Distribution data have been assessed for a variety of fission and corrosion product trace metals at varying uranium concentrations under representative PUREX extraction (3 M HNO3) and stripping (0.1 M HNO3) conditions. As might have been anticipated, the extraction of most trace metals was found to decrease or remain constant with increasing uranium concentration. In contrast, the extraction of some low valence transition metals was found to increase with increasing uranium concentration. The increase in extraction of low valence transition metals may be related to TBP forming reverse micelles instead of recovering uranium as a classical UO2(NO3)(2)(TBP)(2) coordination complex. The low valence transition metals may be being recovered into the cores of the reverse micelles. Also unanticipated was the lack of impact the TBP degradation product, dibutyl phosphate (DBP), had on the recovery of metals in batch distribution studies. This is possibly related to the batch contacts completed in these experiments not adequately recreating the multistage aspects of industrial-scale uranium extraction done using mixer settlers or centrifugal contactors.
引用
收藏
页码:13114 / 13119
页数:6
相关论文
共 50 条
  • [41] A model for the influence of steel corrosion products on nuclear fuel corrosion under permanent disposal conditions
    Wu, L.
    Beauregard, Y.
    Qin, Z.
    Rohani, S.
    Shoesmith, D. W.
    CORROSION SCIENCE, 2012, 61 : 83 - 91
  • [42] Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
    Gonzalez-Robles, E.
    Metz, V.
    Wegen, D. H.
    Herm, M.
    Papaioannou, D.
    Bohnert, E.
    Gretter, R.
    Mueller, N.
    Nasyrow, R.
    de Weerd, W.
    Wiss, T.
    Kienzler, B.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 479 : 67 - 75
  • [43] DIFFUSION MODEL FOR RELEASE OF FISSION PRODUCTS FROM COATED NUCLEAR FUEL PARTICLES
    DUNLAP, RW
    GULDEN, TD
    JOURNAL OF METALS, 1968, 20 (01): : A101 - &
  • [44] ON THE SEPARATION OF FISSION-PRODUCTS FROM NUCLEAR-FUEL WASTE REPROCESSING
    GORSKI, B
    ISOTOPENPRAXIS, 1981, 17 (12): : 416 - 421
  • [45] A numerical methodology for estimation of volatile fission products release from nuclear fuel
    Singh, Mahender
    Mukhopadhyay, Deb
    Datta, D.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 323 : 338 - 344
  • [46] A strategic recovery of rare-metal fission products in spent nuclear fuel
    Sano, Y
    Shinoda, Y
    Ozawa, M
    NUCLEAR TECHNOLOGY, 2004, 148 (03) : 348 - 357
  • [47] Behaviour of fission gases in an irradiated nuclear fuel under a external irradiation
    Desgranges, L
    Ripert, M
    Piron, JP
    Kodja, H
    Gallier, JP
    JOURNAL OF NUCLEAR MATERIALS, 2003, 321 (2-3) : 324 - 330
  • [48] Effect of Redox Conditions on the Fission Products Release from Irradiated Oxide Fuel
    Shcherbina, Natalia S.
    Kivel, Niko
    Guenther-Leopold, Ines
    ATALANTE 2012 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES, 2012, 7 : 104 - 109
  • [50] Estimate of the equilibrium radioactivity of fission products in spent nuclear fuel from the smolensk nuclear power plant
    D. K. Ershov
    Atomic Energy, 1997, 82 : 78 - 79