核设施退役废石墨的处理与处置

Treatment and Disposal of Waste Graphite from Nuclear Facility Decommissioning

石墨有成为核反应堆的慢化剂和反射层的较好的综合性能,早期发展核反应堆的国际原子能机构成员国拥有大量的石墨慢化反应堆,现在要安排退役,退役废石墨的处理和处置,成为人们共同关注的问题。由于废石墨存量大,放射性活度大,它的处理与处置有若干疑难问题有待解决。这些问题的解决关系到环境保护。我国有类似的疑难问题,为此应积极跟踪并开展必要的研究开发工作。

The graphite has composite performance to become moderator and reflector of nuclear reactor. The disposal member states of IAEA possess many graphite reactors developed early, the treatment and of the waste graphite from the decommissioning become a common concerned problem. Since the massive inventory and high radioactivity of the waste graphite several difficult problems in treatment and disposal should be solved urgently. These problems are related to the environmental protection. There are similar difficult problems in our country, therefore the investigation and R＆D work should be done actively.