Journal of Radiation Research and Radiation Proces ›› 2018, Vol. 36 ›› Issue (2): 20101-020101.doi: 10.11889/j.1000-3436.2018.rrj.36.020101

• REVIEW •     Next Articles

Decontamination of tritium from irradiated nuclear graphite

DENG Ke1,2, MA Yuhua1,2, QIN Lailai1,2, LIU Jiayu1,2, ZHANG Qin1,2, MA Zhaowei1,2, YANG Guo1,2, WEI Fei1,2, WANG Guanghua1, LIU Wei1   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China;
    2. University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2018-02-07 Revised:2018-04-02 Online:2018-04-20 Published:2018-04-19
  • Supported by:

    Supported by National Natural Science Foundation of China (21601202)

Abstract:

Due to the operation of nuclear reactors, the nuclear graphite used in these reactors contains large amount of radionuclides. Tritium is considered one of the most important radionuclides, which should be specially treated because of its high concentration and the ease of entering the environment via isotopic reaction with water. According to relevant studies worldwide, thermal treatment is the most applicable technology for the removal of tritium; however, the efficiency of the removal is influenced by the process parameters. The removal temperature should be higher than 600℃, and the removal efficiency increases with increasing flow rate of the carrier gas and upon addition of steam to the carrier gas. Most significantly, the tritium removal efficiency is greatly influenced by the nature and working condition of the graphite. Current research in this field is mostly qualitative. To optimize tritium removal rates, the process should be systematically studied with respect to the different process parameters involved. However, there have been few such studies reported in China. This manuscript summarizes the main findings of various international research groups regarding tritium removal from nuclear graphite, in order to provide some guidance to related domestic researches.

Key words: Decomtamination of nuclear graphite, Thermal treatment, Tritium

CLC Number: 

  • TL75