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Estimation of doses received by operators in the 1958 RB reactor accident using the MCNP5 computer code simulation

机译:使用MCNP5计算机代码模拟估算操作员在1958年RB反应堆事故中获得的剂量

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A numerical simulation of the radiological consequences of the RB reactor reactivity excursion accident, which occurred on October 15, 1958, and an estimation of the total doses received by the operators were run by the MCNP5 computer code. The simulation was carried out under the same assumptions as those used in the 1960 IAEA-organized experimental simulation of the accident: total fission energy of 80 MJ released in the accident and the frozen positions of the operators. The time interval of exposure to high doses received by the operators has been estimated. Data on the RB1/1958 reactor core relevant to the accident are given. A short summary of the accident scenario has been updated. A 3-D model of the reactor room and the RB reactor tank, with all the details of the core, created. For dose determination, 3-D simplified, homogenised, sexless and faceless phantoms, placed inside the reactor room, have been developed. The code was run for a number of neutron histories which have given a dose rate uncertainty of less than 2%. For the determination of radiation spectra escaping the reactor core and radiation interaction in the tissue of the phantoms, the MCNP5 code was run (in the KCODE option) and “mode n p e”, with a 55-group neutron spectra, 35-group gamma ray spectra and a 10-group electron spectra. The doses were determined by using the conversion of flux density (obtained by the F4 tally) in the phantoms to doses using factors taken from ICRP-74 and from the deposited energy of neutrons and gamma rays (obtained by the F6 tally) in the phantoms’ tissue. A rough estimation of the time moment when the odour of ozone was sensed by the operators is estimated for the first time and given in Appendix A.1. Calculated total absorbed and equivalent doses are compared to the previously reported ones and an attempt to understand and explain the reasons for the obtained differences has been made. A Root Cause Analysis of the accident was done and, for the first time, a Cause and Effect diagram has been created in Cause Mapping methodology and shown in Appendix A.2.
机译:通过MCNP5计算机代码对1958年10月15日发生的RB反应堆反应性事故的放射学后果进行了数值模拟,并估算了操作员收到的总剂量。模拟是在与1960年国际原子能机构组织的事故实验模拟所用的相同假设下进行的:事故中释放的80 MJ总裂变能和操作人员的冻结位置。已经估计了操作员接受高剂量暴露的时间间隔。给出了与事故有关的RB1 / 1958反应堆堆芯的数据。事故场景的简短摘要已更新。创建了反应堆室和RB反应堆罐的3-D模型,其中包含堆芯的所有详细信息。为了确定剂量,已经开发了放置在反应器室内的3D简化,均质,无性别和不露面的体模。该代码是针对许多中子历史运行的,这些历史给出了小于2%的剂量率不确定性。为了确定逃逸反应堆堆芯的辐射光谱和幻影组织中的辐射相互作用,运行了MCNP5代码(在KCODE选项中)和“模式npe”,其中具有55组中子光谱,35组伽马射线光谱和10组电子光谱。剂量是通过将体模中的通量密度(由F4理货所获得)转换为使用从ICRP-74以及从体模中的中子和伽马射线沉积能量(由F6理所获得)获得的因子的剂量确定的。 ' 组织。首次对操作员感觉到臭氧气味的时间进行了粗略估算,并在附录A.1中给出。将计算出的总吸收剂量和等效剂量与先前报告的剂量进行比较,并试图理解和解释获得差异的原因。对事故进行了根本原因分析,并且首次在“原因映射”方法中创建了因果图,并在附录A.2中显示。

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