基于某反应堆石墨回取工艺设计及工器具研究
Design of Graphite Retrieval Process and Research on Tools Based on a Certain Reactor
魏峰 1陆博迪1
作者信息
- 1. 中核环保工程设计研究有限公司,北京 100083
- 折叠
摘要
根据 2006 年IAEA-TECDOC-1521《反应堆退役产生放射性石墨的特征、处理与整备》,世界上超过100 座核电反应堆,还有许多研究堆、钚生产堆应用石墨作慢化剂、反射层.许多应用石墨作慢化剂的反应堆已很老旧,其中部分已关闭.放射性石墨的拆除和管理已成为一些IAEA成员国日益重要的任务.本研究根据针对处于不同状态的石墨构件,设计了七种不同的工具头进行石墨回取,为后续工程实施提供技术支持.
Abstract
According to the 2006 IAEA-TECDOC-1521"Characteristics,Treatment,and Preparation of Radioactive Graphite Produced by Reactor Retirement",over 100 nuclear power reactors worldwide,as well as many research and plutonium production reactors,use graphite as a moderator and reflector.Many reactors that use graphite as a moderator are already very old,some of which have been shut down.The dismantling and management of radioactive graphite has become an increasingly important task for some IAEA member states.This study designed seven different tool heads for graphite components in different states.
关键词
石墨/回取/核安全/工器具Key words
graphite/retrieve,nuclear/safety/tools and instruments引用本文复制引用
出版年
2024
NETL
NSTL
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