EXTRACTION CHROMATOGRAPHIC REMOVAL OF NP AND PU DURING THE REPROCESSING OF SPENT TH-U FUEL

被引：1
|
作者：
WENZEL, U
MERZ, E
RITTER, G
机构：
来源：
SEPARATION SCIENCE AND TECHNOLOGY | 1980年 / 15卷 / 04期
关键词：
D O I：
10.1080/01496398008076268
中图分类号：
O6 [化学];
学科分类号：
0703 ;
摘要：
引用
收藏
页码：733 / 743
页数：11
相关论文
共 50 条
  • [1] NEW EXTRACTANTS FOR REPROCESSING OF SPENT TH-U FUEL - EXTRACTION OF U(VI) AND TH(IV) FROM NITRIC-ACID MEDIA BY DI(2-ETHYLHEXYL)SULFOXIDE (DEHSO)
    BAO, BR
    BAO, YZ
    SHEN, CH
    WANG, GD
    QIAN, J
    CAO, ZB
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY-ARTICLES, 1992, 162 (02): : 391 - 398
  • [2] Xe and Kr extraction for Th-U sustainable ICMSR fuel
    Hardiyanti I.S.
    Suparmi A.
    Harto A.W.
    International Journal of Nuclear Energy Science and Technology, 2023, 16 (02) : 108 - 120
  • [3] Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing
    Marchenko V.I.
    Alekseenko V.N.
    Dvoeglazov K.N.
    Radiochemistry, 2015, 57 (04) : 366 - 377
  • [4] Simultaneous quantification of Zr, Mo, U, Np and Pu in technological solutions of spent nuclear fuel reprocessing with a potentiometric multisensor system
    Savosina, Julia
    Agafonova-Moroz, Marina
    Naumov, Andrey
    Nikolaev, Artem
    Lumpov, Alexander
    Babain, Vasily
    Legin, Andrey
    Olivieri, Alejandro
    Parastar, Hadi
    Kirsanov, Dmitry
    SENSORS AND ACTUATORS B-CHEMICAL, 2023, 380
  • [5] Development of spent fuel reprocessing process based on selective sulfurization: Study on the Pu, Np and Am sulfurization
    Kirishima, Akira
    Amano, Yuuki
    Nihei, Toshifumi
    Mitsugashira, Toshiaki
    Sato, Nobuaki
    ACTINIDES 2009, 2010, 9
  • [6] Single-column extraction chromatographic separation of U, Pu, Np and Am
    Morgenstern, A
    Apostolidis, C
    Carlos-Marquez, R
    Mayer, K
    Molinet, R
    RADIOCHIMICA ACTA, 2002, 90 (02) : 81 - 85
  • [7] Startup and burnup strategy for Th-U/U-Pu fuel cycles in an EM2 reactor
    Ma, Y. W.
    Li, X. X.
    Cai, X. Z.
    Yu, C. G.
    Zou, C. Y.
    Han, J. L.
    Chen, J. G.
    PROGRESS IN NUCLEAR ENERGY, 2015, 85 : 764 - 770
  • [8] ACTINIDE PROBLEM IN TH-U FUEL CYCLE
    WENZEL, U
    LASER, M
    MERZ, E
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 351 - 351
  • [9] Uncertainty Analysis of Nuclear Data for Th-U and U-Pu Fuel Cycles in Molten Salt Reactor
    Hu J.
    Wang X.
    Wu J.
    Cai X.
    Han J.
    Chen J.
    Han, Jianlong (hanjianlong@sinap.ac.cn), 2018, Atomic Energy Press (52): : 1206 - 1213
  • [10] Mobility of U, Np, Pu, Am and Cm from spent nuclear fuel into bentonite clay
    Ramebäck, H
    Skålberg, M
    Eklund, UB
    Kjellberg, L
    Werme, L
    RADIOCHIMICA ACTA, 1998, 82 : 167 - 171
12345