HWRR反应堆容器源项计算及退役方案设计  

Calculation of source term of HWRR reactor vessel and preliminary design of decommissioning scheme

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作  者:李睿之[1] 张立军[1] 刘永阔 LI Ruizhi;ZHANG Lijun;LIU Yongkuo(China Institute of Atomic Energy,Beijing 102413,China;Harbin Engineering University,Harbin 150001,China)

机构地区:[1]中国原子能科学研究院,北京102413 [2]哈尔滨工程大学,哈尔滨150001

出  处:《自动化与仪器仪表》2021年第4期86-90,共5页Automation & Instrumentation

基  金:国防科工局“十三五”核设施退役与放射性废物治理专项工程技术研究项目。

摘  要:HWRR反应堆容器是一个放射性强的大型铝合金构件,是反应堆退役源项的重要来源之一,也是反应堆本体退役方案设计的重要内容之一。利用ORIGEN2计算了反应堆容器中子活化源项,同时在容器底部的压力室表面获取了一定量的沉积物样品,通过分析得到了活化源项,反应堆容器主要放射性核素为C-14、Co-60、Ni-63等,总活度为1.77E+12Bq。根据反应堆容器的结构和放射性水平,设计了一套远距离专用切割装置,提出了在反应堆堆外实施切割解体的实施方案,可实现反应堆容器水平和垂直切割,最终完成反应堆容器安全退役。The HWRR reactor vessel is an aluminum alloy component with strong radioactivity and large volume.It is one of the important sources of reactor decommissioning source items and one of the important tasks of the reactor decommissioning plan design.ORIGEN2 was used to calculate the neutron activation source term of the reactor vessel.At the same time,a certain amount of sediment samples was obtained from the surface of the pressure chamber at the bottom of the vessel.The activation source term was obtained through analysis.The main radionuclides of the reactor vessel were C-14 and Co-60,Ni-63,etc.,with a total activity of 1.77 E+12 Bq.According to the structure and radioactivity level of the reactor vessel,a set of special cutting device for remote control is designed,and a preliminary design plan for cutting and dismantling outside the reactor is proposed,which can realize the horizontal and vertical cutting of the reactor vessel and finally decommissioned.

关 键 词:HWRR 反应堆容器 源项 退役方案 

分 类 号:TL943[核科学技术—辐射防护及环境保护]

 

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