用INTERTRAN程序评价我国1988年铀矿石及其浓缩物运输对工作人员和居民的辐射影响

ASSESSMENT OF THE RADIOLOGICAL IMPACT OF TRANSPORTING URANIUM ORE AND CONCENTRATES ON TRANSPORT WORKERS AND THE PUBLIC USING INTERTRAN CODE

本文主要介绍在用国际原子能机构(IAEA)向其成员国提供的 INTERTRAN 程序,对我国1988年铀矿石及浓缩物(重铀酸铵、三碳酸铀酰铵和八氧化三铀)的运输引起的辐射影响进行的评价中参数的确定及其评价结果。分别获取、分析和确定了总长度为14826km 的15条线路(包括铁路和公路)在正常及事故情况下所需的各种输入参数的数值(部分数据采用了该程序给出的缺省数据).在 MICRO VAX-Ⅱ计算机上运行 INTERTRAN 程序。所得的结果表明:在正常运输情况下,关键群体组为装卸工。装卸铀矿石、重铀酸铵、三碳酸铀酰铵、八氧化三铀的人均年剂量当量分别为0.15、0.007、0.04和0.17rem。用热释光剂量计实际测量了某矿的12名铀矿石装卸工的个人剂量,其人均年剂量当量为0.12rem。INTERTRAN 程序计算结果与实测结果较为一致。在事故情况下,早期效应(早期死亡、早期发病)皆为零。潜伏癌症死亡和遗传效应危害的年期望值分别为4.2×10^(-6)和8.0×10^(-9)。

The radiological impact of transportation of uranium ore and concentrates((NH_4)_2U_2O_7,(NH_4)_4UO_2(CO_3)_3 and U_3O_8) in 1988 was assessed using INTERTRANcode The values of inputparameters under normal and accident conditions were acquired,analyzed and determined for 15 transport lines(including railway and road)with total length of14825 km.At the same time,parts of default data given by the code were adopted.Thecode was run on MICRO VAX-Ⅱ computer and the results Were obtained.The results showthat the critical population group is handler group under normal transport conditions.Theyearly average individual dose estimated for handlers who deal with shipments of uranium ore,ammonium diuranate,ammonium uranyl tricarbonate and uranous uranyl oxide are 0.15,0.01,0.04 and 0.17 rem/a,respectively.The average individual dose of 0.12 rem/a for 12uranium ore handlers in a certain ore was measured using TL dosimeters,with Which the resultgiven by INTERTRAN is consistent.Under accident conditions,early effects(early fatalitiesand early morbiditied)are zero.The latent cancer fatality is 4.2×10^(-6) and the genetic effects8.0×10^(-9).The work has laid a foundation for further study of the impact resulted fromradioactive material transports in nuclear fuel cycle system.