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

作　　者：李小华[1] 于涛[1] 夏勇[1] 凌球[1] 

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001

出　　处：《核电子学与探测技术》2012年第8期977-980,共4页Nuclear Electronics & Detection Technology

基　　金：湖南省核技术及应用重点学科;放射性测量与防护技术湖南省高校科技创新团队资助

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。Space dose distribution and inhabitant absorbed dose rate in typical residential area induced by indi- um - 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 at- tenuates 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.

关 键 词：铱-192源 居民区 吸收剂量率 MCNP程序 

分 类 号：R144[医药卫生—公共卫生与预防医学] TL929[核科学技术—核燃料循环与材料]