Sherbini S, Tamasanis D, Sykes J, Porter S W
Health Phys. 1986 Dec;51(6):699-713. doi: 10.1097/00004032-198612000-00001.
A program was developed to calculate the exposure rate resulting from airborne gases inside a reactor containment building. The calculations were performed at the location of a wall-mounted area radiation monitor. The program uses Monte Carlo techniques and accounts for both the direct and scattered components of the radiation field at the detector. The scattered component was found to contribute about 30% of the total exposure rate at 50 keV and dropped to about 7% at 2000 keV. The results of the calculations were normalized to unit activity per unit volume of air in the containment. This allows the exposure rate readings of the area monitor to be used to estimate the airborne activity in containment in the early phases of an accident. Such estimates, coupled with containment leak rates, provide a method to obtain a release rate for use in offsite dose projection calculations.
开发了一个程序来计算反应堆安全壳建筑内空气中气体产生的暴露率。计算是在壁挂式区域辐射监测器的位置进行的。该程序使用蒙特卡罗技术，并考虑了探测器处辐射场的直接和散射分量。发现在50keV时，散射分量约占总暴露率的30%，在2000keV时降至约7%。计算结果被归一化为安全壳内每单位体积空气的单位活度。这使得区域监测器的暴露率读数可用于估计事故早期阶段安全壳内的空气传播活度。这些估计值与安全壳泄漏率相结合，提供了一种获得用于场外剂量预测计算的释放率的方法。
