Thyroid-Gland Irradiation Dose in the Russian Population Due to the Fallout of Radioactive Iodine After the Chernobyl Accident

The average irradiation dose to the thyroid gland is estimated for the people living in 4105 populated points in the Bryanskaya, Tul'skaya, Orlovskaya, and Kaluzhskaya oblasts. The basic principles of the method used to reconstruct the dose are presented. The people living in Bryanskaya oblast have the highest irradiation dose to the thyroid gland: in children less than 3 yr old the individual dose reached 10 Gy; the average dose exceeded 2.5 Gy in 12 populated points. In children living in Bryanskaya oblast, for populated points with soil contamination density above 37 kBq/m² the irradiation dose exceeded 0.05 Gy. The highest average irradiation dose to the thyroid gland in children living in Tul'skaya, Orlovskaya, and Kaluzhskaya oblasts is 0.3–1 Gy. The collective irradiation dose for the four most strongly contaminated oblasts is estimated to be as follows: Bryanskaya – 60, Tul'skaya – 20, Orlovskaya – 13, Kaluzhskaya – 3.5 thousand·people·Gy.     

Examination of 131I and 137Cs releases during late phase of Fukushima Daiichi NPP accident by using 131I/137Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

To investigate what happened in reality during the Fukushima Daiichi Nuclear Power Plant accident, the phenomena within reactor pressure vessel and the discussion of ties with the environmental monitoring measurement are very important. However, the previous study that treats phenomena of the both has not necessarily advanced up to the present time. The source terms predicted by simulation codes such as MELCOR has not yet been consistent with the reverse estimation by WSPEEDI code using environmental measurement data. This study investigated ¹³¹I and ¹³⁷Cs release behaviors during the late phase of the accident to contribute to such examination using the ¹³¹I/¹³⁷Cs ratio of the new source terms predicted by Katata. The ¹³¹I release by the gas–liquid partition from the contaminated water in the 1F2 and 1F3 reactor buildings which was pointed out in the previous study was reevaluated using the new source terms. In addition, paying attention to the similarity of the core conditions between the Fukushima accident and the Phébus FPT3 experiment using the B₄C control rods, the release of organic iodine (CH₃I) during the 1F3 suppression pool venting, formation of CsBO₂ and its release behavior were examined which have not yet been sufficiently studied so far.     

Monte-Carlo方法确定CS-1型131Cs近距离放射治疗源剂量计算参数

针对当前CS-1型¹³¹Cs近距离治疗源剂量计算参数的不一致，根据源的组成和结构，用Monte-Carlo方法（MCNP）计算剂量率常数、径向剂量函数和各向异性函数。其中，剂量率常数计算结果为1.055cGy•h^-1•U^-1，验证了Chen等的γ光谱法实测值（1.066cGy•h^-1•U^-1）和TLD实测值（1.058cGy•h^-1•U^-1）。按AAPMTG43U1的推荐，采用最新的光子截面库（EPDL97）在0.1～10.0cm范围内补充和更新了已报道的径向剂量函数数值，在1.0～7.0cm、0°～90°范围内补充和更新了各向异性函数的相关数值。并对径向剂量函数和各向异性函数进行拟合，得到了实用性较强的经验公式。     

工作人员^131I体内污染测量及剂量估算

本文介绍了用人体计数器测量工作人员~(131)I 体内污染和用 Ge(Li)γ谱仪测量尿中~(131)I 放射性核素的活度。根据实测数据外推求其摄入量,并进行了剂量估算和评价。     

Determination of the average137Cs contamination density of soil

Scientific and Industrial Association “Taifun.” Translated from Atomnaya énergiya, Vol. 76, No. 3, pp. 212–217, March, 1994.     

Research on Rapid Detection Technology of ~(137)Cs and ~(131)I in Vegetables

<正>In this graduation thesis,we adopt theγ-ray spectra analysis with no fractionation method will be applied in detecting radioactive nuclide such as ~(137)Cs,~(131)I in vegetable by the high speed measurement which aim at the limit stipulated of the national standard.Thus,qualitative and quantitative measurement will be used in radioactive nuclide of the sample.     

福岛核事故后上海气溶胶中~(131)I、~(134)Cs和~(137)Cs的来源途径分析

利用对气溶胶中典型放射性核素(~(131)I和134,~(137)Cs)的分析,可以评估福岛核事故产生的放射性物质对上海及全球的大气放射性本底水平造成的影响。本工作结合核事故释放过程、核素的天然衰变以及气象条件等因素,获得核事故期间上海的气溶胶中~(131)I和134,~(137)Cs活度浓度及其比值的分布特征:~(131)I被检出的时间(2011-03-27)早于~(134)Cs(2011-04-06)和~(137)Cs(2011-04-08),~(131)I的活度浓度(0.01~1.20 mBq/m3)比~(134)Cs(0.01~0.58mBq/m3)和~(137)Cs(0.01~0.65mBq/m3)大2~10倍,而且在不同的时间段出现相应的多峰值现象;~(131)I/~(137)Cs活度浓度比值(1.3~10.6)在2011年4月5日之后呈递减趋势,但是~(134)Cs/~(137)Cs活度浓度比值(0.8~2.9)则一直在1.1左右波动。利用HYSPLIT模型模拟放射性气团运移轨迹的分析方法,表明在核事故期间输入到上海的放射性气溶胶的途径有东北和西北两条主要迁移路径。同时通过结合国内相关城市核事故期间大气放射性监测数据,证实了东北路径在中国境内的控制地位。另外,通过总结和分析北半球大气监测数据中~(131)I/~(137)Cs和~(134)Cs/~(137)Cs活度浓度比值最大值的分布特征,验证了日本核事故产生的放射性气溶胶在北半球的传输过程。     

Experimental Estimation of Effective Dose for Irradiation Geometries in Working Places According to ICRP 1990 Recommendations

Conversion coefficients for the equivalent dose in tissue or organ and the effective dose were estimated experimentally with BeO-TLDs inside a male RANDO phantom against external photon radiation. The experiments were performed for Superior-Inferior and Inferior-Superior geometries in cases of unusual irradiation conditions which were occasionally seen in high radiation areas. For these geometries, a parallel photon beam to the long axis of phantom was irradiated. To evaluate the shielding effect of legs in the Inferior-Superior geometry, measurements with and without legs were done by linking a leg phantom, made of tissue equivalent material. The difference of effective dose by the leg phantom was found to be about 20% in the energy range studied.

The effective dose was calculated from the equivalent dose in tissues or organs by modifying the tissue weighting factors given in ICRP Publ. 60 for males, and the effective dose equivalent according to ICRP Publ. 26 was also derived to be compared with the effective dose. In this experiment, the effective dose was estimated lower than the effective dose equivalent about 40% for Superior-Inferior geometry and about 20% for Inferior-Superior geometry due to the change in tissue weighting factors. However, there was no remarkable difference for Anterior-Posterior geometry.     

137Cs辐照和MAP综合处理对猪肉中沙门氏菌的影响

进行了＾１３７Ｃｓ辐照和ＭＡＰ综合处理对沙门氏菌在灭菌猪肉中致死和残存菌生长状况的研究。研究采用反应面设计,并由得到的数据推算回归方程。结果表明,沙门氏菌的致死明显受辐照剂量的影响,残存菌量的对数与辐照剂量成反比：而ＭＡＰ对辐照沙门氏菌的致死无明显影响。５种不同ＣＯ２体积分数对沙门氏菌辐照后的残存菌生长也无明显影响。辐照和ＭＡＰ综合处理并不比单纯辐照能更有效地控制沙门氏菌的致死和残存菌的生长。与空     

与1990年ICRP推荐接轨的内照射剂量估算方法研究及其软件的开发

介绍用于估算个人内照射剂量的新一代计算机应用软件系统。该系统参照ICRP第56、66、67、68、69、71、78号等一系列出版物提供的代谢模型和参数,采用了适于在微机上实现的矩阵算法,使用VC 编制而成,可在Win95或更高版本的微软操作系统下运行。它可以将个人内照射监测量换算为摄入量、有效剂量和其它评价量,适用于职业受照人员的常规个人内照射剂量估算。本套软件采用了新的模型和参数,可以直接求解任何不循环的和循环的库模型。这使得它可用于与1990年ICRP推荐和1997年的国际电离辐射防护和辐射源安全的基本安全标准接轨的个人内照射剂量管理和估算。此外,本套软件在视窗操作系统下运行,图形界面使得它给用户的感觉更加舒服,使用更加方便。     

辐照电子直线加速器辐射剂量测定的技术研究

研究了辐照电子直线加速器辐射剂量测定的技术方法,在测量方法上采取实测与蒙特卡洛模拟计算相结合的方法提高辐射剂量测定的准确度和可操作性;用化学剂量计建立电子束吸收能量测量的方法;用平板电离室建立电子束表面剂量、电子束吸收剂量率测量的方法;用半导体探测器阵列建立电子束辐照均匀性测量的方法。     

131Cs,125I和103Pd近距离治疗源的径向剂量函数研究

临床使用新粒子源近距离治疗之前,需要对粒子源的剂量学参数进行严格确定.本文依照美国医学物理家协会TG43U1推荐的剂量计算公式来研究131Cs,125I和103Pd等近距离治疗粒子源的径向剂量函数.计算中,采用MCNP和EGSnrc两种蒙特卡罗方法;并采用液态水和固体水(Solid Water,WT1)两种材料,粒子源径向研究范围为0.5cm～8cm.在同种粒子源计算结果与前研究的比较中,本研究中在液态和固体水中计算的结果与报道中采用蒙特卡罗计算和TLD测量的结果相当一致.     

中国核动力院外围空气中7Be、40K、60Co、131I、137Cs分布特征及所致公众年有效剂量评价

基于2015—2017年中国核动力院外围空气中⁷Be、⁴⁰K、⁶⁰Co、¹³¹I、¹³⁷Cs监督性监测数据,对综合楼、南坝工会和木城水厂监测点附近居民组三种途径的有效剂量进行了粗略估算。结果表明:随距核设施距离增加,⁶⁰Co、¹³¹I、¹³⁷Cs平均年摄入量和所致年有效剂量减小;综合楼附近居民组中成人、青少年、儿童、幼儿、婴儿经吸入⁷Be、⁴⁰K、⁶⁰Co、¹³¹I、¹³⁷Cs平均年摄入量分别为29.25、26.48、20.16、11.49、6.79 Bq/a;综合楼附近居民组中青少年、儿童、成人、幼儿、婴儿,经吸入、浸没和地面沉积途径⁶⁰Co、¹³¹I、¹³⁷Cs所致年有效剂量分别为133.58、130.98、128.61、120.20、118.61 nSv/a,⁶⁰Co所致剂量分数达到95.6%,其次是¹³⁷Cs;地面沉积途径所致剂量分数达到54%,其次是吸入;综合楼附近居民组中青少年组成员⁶⁰Co、¹³¹I、¹³⁷Cs所致有效剂量最大为133.58 nSv/a,但此有效剂量也仅占评价剂量目标值(0.25 mSv)的1‰以下。由此可以得出,核基地核设施正常运行工况下,⁶⁰Co、¹³¹I、¹³⁷Cs对核基地外围空气的影响很小。     

Measurements of 134Cs and 137Cs in urine and estimation of the inter nal dose of an adult exposed to the Chernobyl Accident

To estimate the internal dose of a Chinese visiting scholar internally contaminated because of the Chernobyl Accident, the contents of 134Cs and 137Cs in urine were measured using a Ge（Li） γ-spectrometer. The internal doses were calculated based on data from the ICRP Publications. The effective doses from ^134Cs and ^137Cs were estimated to be 61 μSv and 98 μ Sv, respectively. The sum of 159 μSv was lower than the total effective dose （310 μSv）, from the inhalation and ingestion of natural radionuclides. The dose of ^131I was also reviewed referring to the UNSCEAR 2000 Report. The equivalent effective dose of ^131I was estimated to be 2.9 mSv, 18 times more than the amount of ^134Cs and ^137Cs. Therefore, it is considered that the earlier estimation of internal doses of ^131I is important in evaluating radiation injuries from a nuclear reactor accident.