节点文献
铱-192工业探伤源对典型居民区的剂量计算
Radiation Dose Calculation of Typical Residential Area Induced by Industrial Radiography Indium-192 Source
【摘要】 根据中国原子能科学研究院铱-192工业探伤源物理参数,采用蒙特卡罗方法程序(MCNP)计算了铱-192源在典型居民区的空间剂量分布和居民的吸收剂量率。结果表明:水平方向1 200 cm处在"有"和"无"混凝土墙防护情况下的吸收剂量率分别为12.200 0和2 090.000 0μGy/h,垂直方向吸收剂量率随位置呈指数衰减;铱-192源所存放2#居民楼3楼层以上住户的吸收剂量率低于USNRC限值。计算结果将为铱-192放射源事故的评估和受照人群的医学治疗提供参考。
【Abstract】 Space dose distribution and inhabitant absorbed dose rate in typical residential area induced by indium-192,which based on physics parameter of China Institute of Atomic Energy industrial radiography indium-192 source is calculated by Monte Carlo methods code MCNP.Results show that horizontal absorbed dose rate with concrete wall is 12.200 0 μGy/h and without it is 2 090.000 0 μGy/h,vertical absorbed dose rate attenuates with exponential law,that absorbed dose rate of inhabitant who bide over 3 floor in 2# dwelling house is under the limit value of USNRC.The calculated results will provide a reference for evaluation of indium-192 source accident and therapeutic treatment of irradiated crowd.
【Key words】 indium-192 source; residential area; absorbed dose rate; MCNP code;
- 【文献出处】 核电子学与探测技术 ,Nuclear Electronics & Detection Technology , 编辑部邮箱 ,2012年08期
- 【分类号】R14;TL77
- 【被引频次】1
- 【下载频次】124