A preliminary study of the reduction of Np(VI) by formohydroxamic acid using stopped-flow near-infrared spectrophotometry

被引:25
作者
Colston, BJ [1 ]
Choppin, GR
Taylor, RJ
机构
[1] De Montfort Univ, Dept Chem, Leicester LE1 9BH, Leics, England
[2] Florida State Univ, Dept Chem, Tallahassee, FL 32306 USA
[3] BNFL Sellafield, Res & Technol, Seascale CA20 1PG, Cumbria, England
关键词
neptunium reduction; formohydroxamic acid; stopped-flow; advanced PUREX process;
D O I
10.1524/ract.2000.88.6.329
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
The kinetics of the reduction of NpO22+ to NpO2+ in nitric acid aqueous solution by formohydroxamic acid (FHA) were studied to allow more accurate flow sheet modelling of neptunium separation from uranium and plutonium in an Advanced PUREX process. The rate of the reaction was monitored using stopped-flow spectrophotometry with near-infrared detection. The conditional reduction rate in 2 M nitric acid at 22 degrees C could be described by the following equation : -d [NpO22+]/dt = k [NpO22+][FHA] (M/s) with k = 1.17 X 10(3) M-1 s(-1) at [H+] = 2.0 M. Comparison with other data available in the literature, indicates that formohydroxamic acid is an unusually strong reducing agent for NpO22+.
引用
收藏
页码:329 / 334
页数:6
相关论文
共 16 条
  • [11] Miles J. H., 1990, SCI TECHNOLOGY TRIBU, VIII
  • [12] The applications of formo- and aceto-hydroxamic acids in nuclear fuel reprocessing
    Taylor, RJ
    May, I
    Wallwork, AL
    Denniss, IS
    Hill, NJ
    Galkin, BY
    Zilberman, BY
    Fedorov, YS
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 1998, 271 : 534 - 537
  • [13] Taylor RJ, 1997, NUCL ENERG-J BR NUCL, V36, P39
  • [14] The reduction of actinide ions by hydroxamic acids
    Taylor, RJ
    May, I
    [J]. CZECHOSLOVAK JOURNAL OF PHYSICS, 1999, 49 : 617 - 621
  • [15] Tikhonov V.S, 1977, RADIOKHIMIYA, V19, P611
  • [16] NEW SEPARATION PROCESS FOR NEPTUNIUM, PLUTONIUM, AND URANIUM USING BUTYRALDEHYDES AS REDUCTANTS IN REPROCESSING
    UCHIYAMA, G
    FUJINE, S
    HOTOKU, S
    MAEDA, M
    [J]. NUCLEAR TECHNOLOGY, 1993, 102 (03) : 341 - 352