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活化石墨处理技术综述
Overview of the Irradiated Graphite Treatment Technology
【摘要】 石墨作为反应堆中的慢化剂和反射层,在核电厂、实验堆、生产堆中均有大量使用,随着这些反应堆的老化和退役,产生了大量的活化石墨,据不完全统计,全球已产生活化石墨约25万吨。活化石墨含多种放射性核素,且其含维格纳能不宜直接处置,活化石墨处理一直是一个世界性难题。近年来,国内外针对活化石墨的处理技术开展了大量研究,包括气化法、部分净化(去污)法、固化法及高温熔盐法等,本文基于活化石墨的来源和特点,对近年来活化石墨处理方法以及研究进展进行了调研和分析,并对并对活化石墨处理研究进行了展望。
【Abstract】 As a moderator and reflector in reactors, graphite is widely used in nuclear power plants, experimental reactors and production reactors. With the aging and decommissioning of these reactors, a large amount of irradiated graphite has been produced. According to incomplete statistics, about 250 000 tons of irradiated graphite have been produced worldwide. The irradiated graphite contains a variety of radionuclides and is not suitable for direct disposal because of its Wigner energy content, so the treatment of the irradiated graphite has been a worldwide challenge. In recent years, a lot of studies have been carried out on the treatment technology of irradiated graphite at home and abroad, including gasification method, partial purification(decontamination) method, solidification method and high temperature molten salt method. In this paper, based on the source and characteristics of the irradiated graphite, the treatment methods and research progress of the irradiated graphite in recent years are investigated and analyzed, and the study on the treatment of irradiated graphite is prospected.
【Key words】 Irradiated graphite; Gasification; Decontamination; Solidification; High temperature molten salt;
- 【文献出处】 核科学与工程 ,Nuclear Science and Engineering , 编辑部邮箱 ,2024年02期
- 【分类号】TL941;TQ127.11
- 【下载频次】23