300#反应堆最终装载燃料组件源项评估  

Source Term Appraisal of the Final Loaded Fuel Assemblies in SPRR-300

作　　者：陈炜[1] 杨锐[1] 胡志勇[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《核电子学与探测技术》2010年第11期1463-1465,1479,共4页Nuclear Electronics & Detection Technology

摘　　要：快速补全运行历史数据库。改进后的ORIGEN2程序及其辅助程序计算流程化,可适应短运行时段。利用其计算多个时刻反应堆最终装载下燃料组件的源项数据,以此确定反应堆乏燃料外运时间表,从而能及早开展反应堆退役相关工作。计算结果提供的数据,是外运时辐射防护评估的主要依据。The database of operation history for SPRR-300 is quickly replenished to make it integrated.The ORIGEN2,which is modified to suit short operation intervals,and its auxiliary programs make the calculation stream-lined.Using the programs,source terms of the final loaded assemblies in SPRR-300 at different moments are calculated.By these data the timetable of transporting all spent fuel assemblies out of SPRR-300 is determined.So the decommissioning work of the reactor can be launched in an early time.The data supplied by this calculation is the main basis for the evaluation of irradiation protection during the transportation.

关 键 词：燃料组件 源项 退役 

分 类 号：TL384[核科学技术—核技术及应用]