Palladium behavior in the presence of irradiated diluent in the PUREX process

被引:2
|
作者
De Sio, S. [1 ]
Klur, I. [2 ]
Tison, E. [3 ]
Bouyer, C. [4 ]
Lebeau, D. [5 ]
Goutelard, F. [5 ]
Sejourne, L. [6 ]
Eysseric, C. [4 ]
Vigier, N. [1 ]
机构
[1] AREVA, NC, DOR, RDP, 1 Pl Jean Millier, F-92084 Paris, France
[2] AREVA, NC, DT, EP,P, La Hague, France
[3] AREVA, NC, DT, EP,EL, La Hague, France
[4] CEA Marcoule, DEN, DRCP, BP 17171, F-30207 Bagnols Sur Ceze, France
[5] CEA Saclay, DEN, DPC, F-91191 Gif Sur Yvette, France
[6] CEA Saclay, DEN, DMN, F-91191 Gif Sur Yvette, France
关键词
palladium; TPH; degradation products; radiolysis; precipitate;
D O I
10.1016/j.proche.2016.10.003
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
AREVA La Hague plants UP3 and UP2-800 started operations to reprocess spent nuclear fuel in 1990 and 1994 respectively. Aging equipment in these plants is a cause for concern as it could lead to process dysfunctions or production rate decrease. A few years ago, several columns had to be replaced in UP3-T4 plutonium purification facility because of clogging. Analyses revealed that TPH degradation products could be responsible for precipitating palladium compounds. 1 M NaOH solutions proved to be efficient to dissolve most of the precipitate. Therefore, several columns in both UP3 and UP2-800 are from now on washed periodically with 1 M NaOH solutions to avoid further clogging and to dissolve current precipitates. (C) 2016 The Authors. Published by Elsevier B.V.
引用
收藏
页码:17 / 23
页数:7
相关论文
共 50 条
  • [1] PUREX DILUENT CHEMICAL DEGRADATION
    TALLENT, OK
    MAILEN, JC
    DODSON, KE
    NUCLEAR TECHNOLOGY, 1985, 71 (02) : 417 - 425
  • [2] BEHAVIOR OF TRITIUM IN THE PUREX PROCESS
    UCHIYAMA, G
    FUJINE, S
    MAEDA, M
    SUGIKAWA, S
    TSUJINO, T
    SOLVENT EXTRACTION AND ION EXCHANGE, 1995, 13 (01) : 59 - 82
  • [3] DILUENT DEGRADATION PRODUCTS IN THE PUREX SOLVENT
    NEACE, JC
    SEPARATION SCIENCE AND TECHNOLOGY, 1983, 18 (14-1) : 1581 - 1594
  • [4] BEHAVIOR OF NEPTUNIUM IN THE PUREX PROCESSING OF HIGHLY IRRADIATED FUELS
    OCHSENFELD, W
    BLEYL, HJ
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1979, (APR): : 30 - 30
  • [5] Behavior of uranium in the partitioning process of PUREX reprocessing
    Tsukada, Takeshi
    Takahashi, Keiju
    Yoshiki, Nobuya
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (02) : 179 - 194
  • [6] ON THE EXTRACTION BEHAVIOR OF TECHNETIUM WITH RESPECT TO THE PUREX PROCESS
    KANELLAKOPULOS, B
    KONIG, CP
    RADIOCHIMICA ACTA, 1983, 33 (2-3) : 169 - 175
  • [7] Identification of diluent degradation products in radiolyzed PUREX solvent
    Mishra, Satyabrata
    Soda, Anil Kumar
    Sridhar, Madabhushi
    Mallika, C.
    Pandey, N. K.
    Mudali, U. Kamachi
    SOLVENT EXTRACTION AND ION EXCHANGE, 2018, 36 (01) : 54 - 65
  • [8] PUREX PROCESS FOR REPROCESSING OF IRRADIATED NUCLEAR-FUELS AND POSSIBLE ALTERNATIVES
    不详
    CHEMIKER-ZEITUNG, 1979, 103 (06): : 229 - 230
  • [9] The behavior of technetium in technetium-scrubbing stage of PUREX process
    Liu, Fang
    Zheng, Wei-fang
    Zhang, Yu
    Wang, Hui
    Zhou, Chang-xin
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2013, 295 (03) : 1621 - 1625
  • [10] The behavior of technetium in technetium-scrubbing stage of PUREX process
    Fang Liu
    Wei-fang Zheng
    Yu Zhang
    Hui Wang
    Chang-xin Zhou
    Journal of Radioanalytical and Nuclear Chemistry, 2013, 295 : 1621 - 1625