Precipitation behaviour of simulated high-level liquid waste during the denitration process based on two-step vitrification

被引:0
|
作者
Wang, Changfu [1 ,2 ]
Liu, Xu [2 ]
Shao, Bobo [3 ]
Xu, Zhiyi [2 ]
Liu, Yan [2 ]
Wang, Yun [2 ]
Tan, Shengheng [4 ]
Liu, Zhirong [2 ]
Zhang, Shengdong [4 ]
机构
[1] East China Univ Technol, Engn Res Ctr Nucl Technol Applicat, Minist Educ, Nanchang 330013, Peoples R China
[2] East China Univ Technol, Sch Nucl Sci & Engn, Nanchang 330013, Peoples R China
[3] China Nucl Power Engn Co Ltd, Dept Sci & Technol, Beijing 100840, Peoples R China
[4] China Inst Atom Energy, POB 275-93, Beijing 102413, Peoples R China
关键词
High-level liquid waste; Vitrification; Denitration; Precipitation; ZIRCONIUM MOLYBDATE; FORMIC-ACID; VOLATILIZATION; RUTHENIUM; TEMPERATURE; SYSTEMS; METALS; CESIUM;
D O I
10.1016/j.nucengdes.2023.112739
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 the two-step vitrification process, it is necessary to first reduce the acidity of the waste before calcination. In this study, the influence of formic acid as a denitration agent on the precipitation behavior of a simulated highlevel liquid waste during denitration was investigated. The denitration process was conducted at a temperature of 90celcius, and the denitration ratio ranged from 1.0 to 2.0. The denitration products were analyzed using various techniques including ICP-OES, XRF, SEM-EDS, Raman, and XRD. The results revealed a significant decrease in nitrate content after denitration when the denitration ratio was between 1.0 and 2.0. As the denitration ratio increased, the nitrate content progressively decreased, while the formic acid content increased. A denitration precipitate containing elements such as Zr, Mo, La, Ce, Nd, Fe, Te, Pr, Cs, Sm, Sr, Y, Co, and Ni was observed. The content of each component and the morphology of the precipitate were found to be correlated with the denitration ratio. Crystallization of MoO2 and Ln2Zr3(MoO4)9 (Ln = La, Ce, Nd, Pr, Sm) in the precipitation occurred when the denitration ratio was between 1.0 and 1.2. On the other hand, predominantly rod-shaped particles (Ln (HCOO)3, Ln = La, Ce, Pr, Nd, Sm) were formed when the denitration ratio was 1.4 or higher.
引用
收藏
页数:7
相关论文
共 50 条
  • [21] Processing simulated oxalated high-level waste through a vitrification feed preparation flowsheet
    Patello, GK
    Russell, RL
    Golcar, GR
    Smith, HD
    Smith, GL
    Elliott, ML
    ENVIRONMENTAL ISSUES AND WASTE MANAGEMENT TECHNOLOGIES IN THE CERAMIC AND NUCLEAR INDUSTRIES IV, 1999, 93 : 163 - 170
  • [22] Decontamination of high-level waste using a continuous precipitation process
    Peterson, RA
    Burgess, JO
    Walker, DD
    Hobbs, DT
    Serkiz, SM
    Barnes, MJ
    Jurgensen, AR
    SEPARATION SCIENCE AND TECHNOLOGY, 2001, 36 (5-6) : 1307 - 1321
  • [23] DEVELOPMENT OF VITRIFICATION TECHNIQUE OF HIGH-LEVEL LIQUID WASTE IN ENGINEERING SCALE AT PNC
    OGUINO, N
    TSUNODA, N
    SEGAWA, T
    AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 320 - 320
  • [24] GENERATION AND VITRIFICATION OF HIGH-LEVEL LIGHT WATER-REACTOR LIQUID WASTE
    WHEELWRIGHT, EJ
    BJORKLUND, WJ
    BROWNE, LM
    BRYAN, GH
    HOLTON, LK
    IRISH, ER
    SIEMENS, DH
    NUCLEAR TECHNOLOGY, 1982, 58 (02) : 271 - 293
  • [25] DEVELOPMENT OF A MICROWAVE-POWERED VITRIFICATION PROCESS FOR HIGH-LEVEL WASTE IMMOBILIZATION
    ALLEN, PL
    FORD, LH
    HARDWICK, WH
    GAYLER, R
    AMERICAN CERAMIC SOCIETY BULLETIN, 1981, 60 (03): : 368 - 368
  • [26] EFFECT OF PLATINUM GROUP ELEMENTS ON DENITRATION OF HIGH-LEVEL LIQUID WASTE WITH FORMIC-ACID
    NAKAMURA, H
    YAMAGUCHI, I
    KUBOTA, M
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1978, 15 (10) : 760 - 764
  • [27] Removal of nitric acid from a simulated high level liquid waste by a safe chemical denitration
    Y. Kondo
    Journal of Radioanalytical and Nuclear Chemistry, 1999, 242 : 505 - 513
  • [28] Removal of nitric acid from a simulated high level liquid waste by a safe chemical denitration
    Kondo, Y
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 1999, 242 (02) : 505 - 513
  • [30] Progress in Research and Development of Vitrification Technology for High-level Radioactive Liquid Waste at CIAE
    Li Y.
    Zhang S.
    Xian L.
    Liu L.
    Tan S.
    Zhang H.
    Zhou H.
    Qie D.
    Zhang, Shengdong (zhangsd@ciae.ac.cn), 1600, Atomic Energy Press (54): : 126 - 136