首页|基于某反应堆石墨回取工艺设计及工器具研究

基于某反应堆石墨回取工艺设计及工器具研究

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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.
Design of Graphite Retrieval Process and Research on Tools Based on a Certain Reactor
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.

graphiteretrieve,nuclearsafetytools and instruments

魏峰、陆博迪

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中核环保工程设计研究有限公司,北京 100083

石墨 回取 核安全 工器具

2024

广东化工
广东省石油化工研究院

广东化工

影响因子:0.288
ISSN:1007-1865
年,卷(期):2024.51(10)
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