Study of Pressing Molding Technology for Fast Reactor Fuel Pellet

被引：0
|
作者：
Zhu T. [1 ]
Zhang S. [1 ]
Wu J. [1 ]
Zhang Y. [1 ]
机构：
[1] The 404 Company Limited, CNNC, Lanzhou
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2020年 / 54卷 / 05期
关键词：
Bidirectional pressing; Fast reactor; Fuel element; Fuel pellet; Pellet property;
D O I：
10.7538/yzk.2019.youxian.0506
中图分类号：
学科分类号：
摘要：
MOX fuel pellets were prepared by bidirectional pressing. Through a series of experiments, the influence of pressing pressure, dwell time and addition amount of lubricants on the performance of fuel pellets was studied. A set of pressing technological parameters of fast reactor fuel pellet were obtained. The pressing pressure is 400 MPa, the dwell time is 2 s, and the content of zinc stearate is 0.4%. The results of the verification test show that the green billet made by the above process parameters is of good quality. The microstructure of the sintered pellets is uniform and there are no macro and micro defects, and the sintered pellets can be used in the manufacture of fuel pellets in fast reactor, and can be used as a reference for the manufacture of other types of fuel element pellets. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码：835 / 841
页数：6
相关论文
共 10 条
  • [1] Wick O.J., Plutonium Handbook, (1967)
  • [2] Liu J., Improved design of pelleting andpressing process for PWR components production, Atomic Energy Science and Technology, 37, pp. 36-39, (2003)
  • [3] Li Y., Dai S., Yang J., Et al., Study on preparation technology of hollow pellet of combustible poison in zirconium carbide alloy, Nucler Power Engineering, 34, 3, pp. 28-31, (2013)
  • [4] Tian C., The influence of fuel pellet microstructure on pellet manufacturing quality was analyzed, Science & Technology Vision, 21, pp. 19-20, (2016)
  • [5] Chen L., Ren Y., Li A., Et al., Study on high temperature sintered thorium dioxide pellet technology, Atomic Energy Science and Technology, 49, pp. 438-442, (2015)
  • [6] Jayaraj V.V., Thirunavukkarasu S., Anandaraj V., Et al., Evaluation of fuel-clad chemical interaction in PFBR MOX test fuel pins, Journal of Nuclear Materials, 509, pp. 33-35, (2018)
  • [7] Balboa H., Van Brutzel L., Chartier A., Et al., Damage characterization of (U, Pu)O<sub>2</sub> under irradiation by molecular dynamics simulations, Journal of Nuclear Materials, 11, pp. 23-26, (2018)
  • [8] Berg-Lindell M., Andersson P., Grape S., Et al., Discrimination of irradiated MOX fuel from UO<sub>2</sub> fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes, Nuclear Instruments and Methods in Physics Research Section A, 885, pp. 67-78, (2018)
  • [9] Mahmood T., Riaz M., Omar M.H., Et al., Alternative methods for the simultaneous monitoring of simple linear profile parameters, The International Journal of Advanced Manufacturing Technology, 97, pp. 5-8, (2018)
  • [10] Bernal A., Roman J.E., Miro R., Et al., Multigroup neutron diffusion equation with the finite volume method in reactors using MOX fuels, Journal of Nuclear Science and Technology, 54, pp. 10-11, (2017)
1