The recovery of uranium from the waste solution of fission 99Mo production

被引：5
|
作者：
Hladik, O. [1 ]
Bernhard, G. [1 ]
Boessert, W. [1 ]
机构：
[1] Central Institute of Nuclear Research, 8051 Dresden, German Democratic Republic
来源：
International journal of radiation applications and instrumentation. Part A, Applied radiation and isotopes | 1987年 / 38卷 / 08期
关键词：
FISSION MOLYBDENUM PRODUCTION - TRI-N-BUTYLPHOSPHATE - WASTE SOLUTION;
D O I：
10.1016/0883-2889(87)90127-4
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：619 / 622
相关论文
共 50 条
  • [1] THE RECOVERY OF URANIUM FROM THE WASTE SOLUTION OF FISSION MO-99 PRODUCTION
    HLADIK, O
    BERNHARD, G
    BOESSERT, W
    GRAHNERT, T
    MUNZE, R
    APPLIED RADIATION AND ISOTOPES, 1987, 38 (08) : 619 - 622
  • [2] Initial development of an alkaline process for recovery of uranium from 99Mo production process waste residue
    Lize Stassen
    Janine Suthiram
    Journal of Radioanalytical and Nuclear Chemistry, 2015, 305 : 41 - 50
  • [3] Initial development of an alkaline process for recovery of uranium from 99Mo production process waste residue
    Stassen, Lize
    Suthiram, Janine
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2015, 305 (01) : 41 - 50
  • [4] Separation of fission 99Mo from irradiated uranium using differential volatility
    S. P. Hasilkar
    R. B. Manolkar
    A. V. Jadhav
    Journal of Radioanalytical and Nuclear Chemistry, 2002, 251 : 277 - 280
  • [5] Separation of fission 99Mo from irradiated uranium using differential volatility
    R. B. Manolkar
    S. P. Hasilkar
    A. V. Jadhav
    Journal of Radioanalytical and Nuclear Chemistry, 2002, 251 (2) : 273 - 276
  • [6] Separation of tungsten from LEU fission-produced 99Mo solution to improve technological performance in both the processes of 99Mo and 99mTc generator production
    Van So Le
    Cong Duc Nguyen
    Minh Khoi Le
    Journal of Radioanalytical and Nuclear Chemistry, 2015, 303 : 1123 - 1127
  • [7] Separation of tungsten from LEU fission-produced 99Mo solution to improve technological performance in both the processes of 99Mo and 99mTc generator production
    Van So Le
    Cong Duc Nguyen
    Minh Khoi Le
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2015, 303 (02) : 1123 - 1127
  • [8] Separation of 99Mo from a simulated fission product solution by precipitation with α-benzoinoxime
    Hwang, DS
    Choung, WM
    Kim, YK
    Park, JH
    Park, SJ
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2002, 254 (02) : 255 - 262
  • [9] Development of fission 99Mo production process using HANARO
    Lee, Seung-Kon
    Lee, Suseung
    Kang, Myunggoo
    Woo, Kyungseok
    Yang, Seong Woo
    Lee, Junsig
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (07) : 1517 - 1523
  • [10] Evaluation of efficient cementation of fission 99Mo production process waste and feasibility disposal of cement waste form
    Shon, Jong Sik
    Kim, Gi Yong
    Im, Junhyuck
    ANNALS OF NUCLEAR ENERGY, 2019, 124 : 342 - 348
12345