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Radiological safety analysis of the SAMOP reactor experimental facility

机译:Samop反应器实验设施的放射性安全分析

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The reactor subcritical assembly for 99Mo production(SAMOP)experimental facility is a nuclear reactor operating under subcritical conditions.SAMOP reactor is fueled by uranyl nitrate inside an annular tube surrounded by the TRIGA reactor fuels.The external neutron source required for the SAMOP reactor operation comes from the Kartini reactor radial beam-port.The aim of the analysis is to determine the estimated personnel radiation dose for normal conditions and severe postulated accident.The analysis methods is a calculation of source term,radiation propagation to the surrounding area,and estimation of personnel radiation dose rate for normal and severe accident conditions.The analysis result shows that the effective radiation dose received by personnel in the working area of the SAMOP reactor is below the dose limit for radiation worker at the Kartini reactor,i.e.7 μSv/h.Whereas,in the postulated severe accident condition,the highest exposure rate at 1 m above and beside the reactor cooling tank are 4.19 mSv/h and 1.35 mSv/h respectively.
机译:用于99MO生产(SAMOP)实验设施的反应器亚临界组件是在亚临界条件下操作的核反应堆。通过硝酸盐在由Triga反应器燃料包围的环形管内通过硝酸盐燃料。Samop反应器操作所需的外部中子源从Kartini反应堆径向射线端口。分析的目的是确定估计的人员辐射剂量,用于正常情况和严重假设事故。分析方法是计算源期限,辐射传播到周边地区,以及估计人员辐射剂量率对于正常和严重的事故条件。分析结果表明,Samop反应器的工作区域中的人员接收的有效放射剂量低于Kartini反应器的辐射工人的剂量限制,IE7μSV/ h。而且,在假定的严重事故条件下,最高曝光率在1米以上和反应器C旁边OOLING罐分别为4.19 msv / h和1.35 msv / h。

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