目的研制一种用于全身计数器刻度的简化体模;方法根据全身计数器刻度的过程与方法,建立了一种用于全身计数器刻度的简化体模设计方法,并利用蒙卡程序设计了一个包含全身、甲状腺、肺部和胃肠道4个器官的简化体模用于ORTEC-Stand FAST I...目的研制一种用于全身计数器刻度的简化体模;方法根据全身计数器刻度的过程与方法,建立了一种用于全身计数器刻度的简化体模设计方法,并利用蒙卡程序设计了一个包含全身、甲状腺、肺部和胃肠道4个器官的简化体模用于ORTEC-Stand FAST II全身计数器的刻度,通过实验测量对该简化体模与BOMAB模型进行测量比较。结果在50 keV到2 MeV范围内,全身计数器对简化体模与BOMAB体模相同器官内相同能量射线探测效率的模拟数据的误差在5%以内,实验测量结果的误差在10%以内。结论本工作研制了一款用于全身计数器刻度的简化体模,验证了用简化体模替代物理人体模型对全身计数器进行刻度的可行性,可为内照射监测中全身计数器的刻度提供极大的便利。展开更多
The 124Sb in vivo exposed person is measured with whole-body counter. Thesolid point source method is applied to calibrate the counter. The minimum detectable activity of this system for 124Sb is 32 Bq.
It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the ...It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the software of controlling, interface and internal dose estimation programs to the original iron cabin shielding whole-body counter. The preliminary application shows that its data processing is rapid and correct, and can meet the requirement of rapid internal radioactive contamination monitoring and diagnosing in case of lots of internal contamination subjects happened innuclear accident.展开更多
文摘目的研制一种用于全身计数器刻度的简化体模;方法根据全身计数器刻度的过程与方法,建立了一种用于全身计数器刻度的简化体模设计方法,并利用蒙卡程序设计了一个包含全身、甲状腺、肺部和胃肠道4个器官的简化体模用于ORTEC-Stand FAST II全身计数器的刻度,通过实验测量对该简化体模与BOMAB模型进行测量比较。结果在50 keV到2 MeV范围内,全身计数器对简化体模与BOMAB体模相同器官内相同能量射线探测效率的模拟数据的误差在5%以内,实验测量结果的误差在10%以内。结论本工作研制了一款用于全身计数器刻度的简化体模,验证了用简化体模替代物理人体模型对全身计数器进行刻度的可行性,可为内照射监测中全身计数器的刻度提供极大的便利。
文摘The 124Sb in vivo exposed person is measured with whole-body counter. Thesolid point source method is applied to calibrate the counter. The minimum detectable activity of this system for 124Sb is 32 Bq.
文摘It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the software of controlling, interface and internal dose estimation programs to the original iron cabin shielding whole-body counter. The preliminary application shows that its data processing is rapid and correct, and can meet the requirement of rapid internal radioactive contamination monitoring and diagnosing in case of lots of internal contamination subjects happened innuclear accident.
