摘要
为了快速评价核应急人员现场剂量,建立了核事故下西安脉冲堆核应急人员现场剂量理论计算方法,以西安脉冲堆厂址特征、事故源项参数为输入数据,计算了核事故下核应急响应人员现场受照个人有效剂量。计算结果表明:在设计基准事故下,厂内应急人员的所受事故个人有效剂量较低,仅为1.78 mSv左右;在极端假设事故下,以8 h工作时间计算时受照事故剂量为100 mSv以上。场区内应急监测人员受照剂量相对厂房内的小得多,在35 m、100 m边界所受个人有效剂量分别为7.97×10-6、9.95×10-2mSv。理论计算结果可以作为核事故应急的技术数据,所建立的评价方法程序可运用于实际的核事故应急剂量评价中。
In order to rapidly assess individual dose of on-site nuclear accident emergency, a theoretical calculation method for Xi＇ an pulsed reactor nuclear accident emergency was established. Individual dose of response staff was calculated based on the characteristic parameter of XAPR and source items as input data. The results demonstrated that in case of design basis accident individual dose that operation and response staff received in reactor building is very limited, just about 1.78 mSv. In case of extreme hypothesis accident it was above 100 mSv considering 8 hours＇ working, and dose that emergency environmental monitoring staff received was lower compared to dose inside building, it was 7.97 × 10^-6 and 9.95 × 10^-5 mSv at 35 m and 100 m boundary from the reactor site respectively. The results could be used as technological data of nuclear accident emergency, and the method could be applied in individual dose assessment of nuclear emergency in practice.
出处
《辐射防护》
CAS
CSCD
北大核心
2014年第2期91-96,101,共7页
Radiation Protection
关键词
核应急
大气扩散
剂量
计算
nuclear emergency
atmospheric dispersion
dose
calculation
