Examination for Neutron Dose Assessment Method from Induced Sodium-24 in Human Body in Criticality Accidents
Examination for Neutron Dose Assessment Method from Induced Sodium-24 in Human Body in Criticality Accidents
复制标题
临界事故中24钠诱导人体内中子剂量评估方法的检验
DOI：
10.1080/18811248.2005.9726404
复制
发表时间：
2005
影响因子：
1.2
通讯作者：
Y. Yamaguchi
中科院分区：
文献类型：
--
作者：
F. Takahashi;A. Endo;Y. Yamaguchi
对临界事故中人体内活性钠剂量估算方法进行了实验验证。在瞬态实验临界装置中，对含有氯化钠溶液的平板体模进行辐照，以模拟体内钠的活化。通过Monte Carlo计算，得到了中子释放带电粒子在体模位置引起的24 Na比活度与中子剂量之间的定量关系。在以前的工作中，24 Na在软组织中的比活度到全身剂量的转换系数已被分析与MCNP-4 B程序有关的中子能谱在一些假设的配置与燃料和周围材料。其中一个准备的转换系数被应用于评估中子剂量从测量的放射性的24 Na。估算的剂量与本研究中通过蒙特卡罗计算分析的剂量一致，在国际原子能机构指出的事故初始剂量确定的可接受不确定度内。此外，根据诱导24 Na的量，用准备的系数评估的剂量接近于先前用临界事故剂量计测量的值。
Experiments were made to verify a dose assessment method from activated sodium in human body in criticality accidents. A slab phantom containing sodium chloride solution was irradiated in the Transient Experiment Critical Facility to simulate activation of sodium in body. Monte Carlo calculations were performed to obtain quantitative relation between the specific activity of induced 24Na and neutron dose, which was imparted by charged particles liberated by neutrons, at the phantom position. In the previous work, conversion coefficients from specific activity of 24Na in soft tissue to whole body dose had been analyzed with the MCNP-4B code concerning neutron spectra at some hypothesized configurations with fuel and surrounding materials. One of the prepared conversion coefficients was applied to evaluate neutron dose from the measured radioactivity of 24Na. The estimated dose agreed with the dose analyzed by the Monte Carlo calculations in the present study within an acceptable uncertainty for initial dose determination in an accident, which is indicated by the International Atomic Energy Agency. In addition, the dose assessed with the prepared coefficient from the quantity of induced 24Na was close to a value, which had been previously measured with dosimeters for criticality accidents.