西安脉冲堆失水事故后堆顶平台散射γ剂量率计算  

Dose Calculation for Pool Water Loss Accident of Xi’an Pulsed Reactor

作　　者：沈瑾[1] 赵科[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》1999年第5期459-461,共3页Nuclear Power Engineering

摘　　要：计算了西安脉冲堆发生失水事故后， 堆芯发射的γ射线因失去堆水池屏蔽层， 直接穿透空气， 被顶部天花板反散射后在堆水池平台产生的辐射剂量率。计算结果与ＴＲＩＧＡ２ 堆结果相符合， 是确定事故后工作人员在平台可停留时间的基础， 同时为适当地制定事故处理措施提供了参考。In the pool water loss accident of pulsed reactor,gamma ray from the core penetrates directly through the air and be reflected and scattered by the roof So the limited period calculation for the staffs who need to stay at the reactor pool top platform is important to reduce the exposed dose and keep the safety This calculation is giving the scattered dose rate on the reactor pool top platform and the maximum staying time for the staffs there after the pool water loss accident

关 键 词：脉冲堆 散射辐射 Γ剂量率 失水事故 

分 类 号：TL411.406[核科学技术—核技术及应用] TL73