Dissolution behavior of pulverized irradiated fuels in nitric acid solutions

被引:5
作者
Ikeda, Y [1 ]
Yasuike, Y
Nishimura, K
Hasegawa, S
Mason, C
Bush, R
Takashima, Y
机构
[1] Inst Res & Innovat, Kashiwa Lab, Kashiwa, Chiba 2770861, Japan
[2] Mitsubishi Mat Corp, Naka, Ibaraki 3110102, Japan
[3] AEA Technol Plc, Harwell OX11 0RA, Berks, England
关键词
nuclear fuel reprocessing; dissolution; irradiated nuclear fuels; pulverized nuclear fuels; nitric acid; nitrous acid; head-end process; solubility;
D O I
10.1080/18811248.1999.9726218
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In order to examine the dissolution behavior of pulverized irradiated fuels, approximately 1g of powdery irradiated fuels (burnup: 50 GWd/t, cooling time: more than 15 yr, size: 90-150, 300-355, and 850-1,000 mu m) was weighed out accurately and dissolved in HNO3 solutions (300 cm(3)) stirred at 300 rpm. The dissolution reactions were followed by measuring [UO22+] and [HNO2] in dissolvent solutions. Dissolution ratios were calculated as percentage of [weight of uranium dissolved]/[initial weight of uranium in fuels]. It was found that the powdery irradiated fuels are dissolved easily even at room temperature in 3-4 M (mol/dm(3)) HNO3 solutions and much more rapidly than non-irradiated UO2 powders (95% theoretical density). These results indicate that the pulverization of irradiated fuels is effective for malting the dissolution conditions mild. Furthermore, the difference in dissolution behavior between powdery non- and irradiated fuels were suggested to he due to the difference in their densities, the acceleration effect of certain fission products in irradiated fuels, or the participation of oxidants other than HNO2 and NO3- in dissolution reactions of irradiated fuels.
引用
收藏
页码:358 / 363
页数:6
相关论文
共 16 条
  • [1] ADACHI T, 1991, 91010 JAERI M
  • [2] Kinetic studies on dissolution of UO2 powders in acid solutions by using cerium(IV) or chlorine dioxide as oxidants
    Asano, Y
    Kataoka, M
    Tomiyasu, H
    Ikeda, Y
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1996, 33 (02) : 152 - 156
  • [3] ASANO Y, 1995, PROG NUCL ENERG, V29, P243
  • [4] O-17 NMR-STUDY ON DISSOLUTION REACTION OF UO2 IN NITRIC-ACID - MECHANISM OF ELECTRON-TRANSFER
    IKEDA, Y
    YASUIKE, Y
    TAKASHIMA, Y
    PARK, YY
    ASANO, Y
    TOMIYASU, H
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1993, 30 (09) : 962 - 964
  • [5] ACCELERATION EFFECT OF NOBLE-METALS ON DISSOLUTION RATE OF UO2 POWDERS IN NITRIC-ACID
    IKEDA, Y
    YASUIKE, Y
    TAKASHIMA, Y
    NISHIMURA, K
    HASEGAWA, S
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1993, 30 (05) : 485 - 487
  • [6] KINETIC-STUDY ON DISSOLUTION OF UO2 POWDERS IN NITRIC-ACID
    IKEDA, Y
    YASUIKE, Y
    NISHIMURA, K
    HASEGAWA, S
    TAKASHIMA, Y
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1995, 224 (03) : 266 - 272
  • [7] MECHANISM OF THE OXIDATIVE DISSOLUTION OF UO2 IN HNO3 SOLUTION
    INOUE, A
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1986, 138 (01) : 152 - 154
  • [8] SPECTROPHOTOMETRIC DETERMINATION OF URANIUM(VI) WITH 2-(5-BROMO-2-PYRIDYLAZO)-5-DIETHYLAMINOPHENOL
    JOHNSON, DA
    FLORENCE, TM
    [J]. ANALYTICA CHIMICA ACTA, 1971, 53 (01) : 73 - &
  • [9] EFFECT OF NITROUS-ACID ON DISSOLUTION OF UO2 POWDERS IN NITRIC-ACID OPTIMAL CONDITIONS FOR DISSOLVING UO2
    NISHIMURA, K
    CHIKAZAWA, T
    HASEGAWA, S
    TANAKA, H
    IKEDA, Y
    YASUIKE, Y
    TAKASHIMA, Y
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1995, 32 (02) : 157 - 159
  • [10] SHABBIR M, 1969, J APPL CHEM, V19, P52