福岛第一核电厂事故源项估算及方法比较

Fukushima Dai-ichi NPP Accident Source Term Estimation and Methods Comparison

本文参考日本福岛第一核电厂的部分资料,利用美国核管会发布的《轻水堆核电厂事故源项》(NUREG-1465)以及国际原子能机构发布的《为轻水堆设计估算参考源项所提供的简化方法》(IAEA-TECDOC-1127)两份技术文件中的假设条件,分别计算出事故后由堆芯释放到安全壳内的放射性源项。同时通过对堆芯积存量、抑压水池净化因子等参数的估计,得出较为保守的环境释放源项。采用有关技术文件所提供的剂量计算模式及剂量转换因子对事故剂量后果做了估算,并比较、分析了两种假设条件下计算出的堆芯释放源项及其对事故剂量后果的影响。本文对核电厂发生严重事故时快速确定堆芯释放源项并估算事故剂量后果具有一定的参考意义。

This paper calculates the conservative radioactive source term released to the containment based on the assumptions specified in NUREG-1465 and IAEA-TECDOC-1127, using some of the available information of Fukushima Dai-ichi NPP. A series of environmental release source terms is obtained with the consideration of the parameters such as the cumulative amount of the radioactive material and the de- contamination factor in suppression pool. Moreover, this paper calculates the equivalent dose after accident using the models and parameters in some related technical documents. The containment radioactive relea- ses and the resultant doses, which are based on two assumptions mentioned above, are analyzed and com- pared. In conclusion, this paper does make sense for the quick establishment of the severe accident source term and the accident consequences estimation in nuclear power plant.