一种核电站事故工况下安全壳内剂量率的估算方法

目的 通过估算冷却剂丧失事故(LOCA)时间内的安全壳内剂量率,推测事故的大小和发展趋势,为防止事故扩大、保护公众辐射安全提供依据。方法 根据国内某核电站安全分析报告及LOCA事故应急演习的实际情况基础上,提出了冷却剂丧失事故工况序列MCNP耦合计算方法,将该计算方法用于LOCA事故实际演习边界条件计算。结果 计算结果与现场事故期间安全壳内γ辐射剂量率监测通道的实际读数比对,数据匹配较好。结论 该计算方法经验证可以用于类似事故工况下安全壳内剂量率的估算,为事故工况下安全壳内的放射性变化情况提供参考。

An Estimation Method of Dose Rate in the Containment under the Accident Operating State

Objective To provide speculate the size and development trend of accident, prevent the expanding of accident and protect the public radiation safety by estimating the dose rate in the containment within the period of LOCA. Methods This work is on the basis of safety analysis report of some domestic nuclear power plant and actual condition of LOCA accident emergent manoeuvre to bring forward MCNP coupling calculation method of operating condition sequence of accident losing coolant, which is used in the calculation of LOCA accident actual manoeuvre boundary condition. Results With the comparison of the calculation results and actual readings of gamma radiation dose rate monitoring channel in the containment during the on-site accident, data match well. Conclusion By the verification, this calculation method can be used to make the estimation of dose rate in the containment under the analog accidental operating condition and provide the references for the radioactivity alteration in the containment under the accidental operating condition.