辐射化学剂量计在强脉冲混合辐射场测定中的应用

本文讨论了将硫酸亚铁剂量计和铜－铁剂量计用于强脉冲混合辐射场测定的实验设计,利用直径２２０毫米的聚乙烯球,将硫酸亚铁剂量计的快中子响应降低到２０％以下,由它和完全暴露在中子、γ混合场中的硫酸亚铁剂量计响应之差,测量中子吸收剂量。这种方法两次实际用于强脉冲混合辐射场中子、γ吸收剂量测量,得到的结果和热释光剂量计、固体径迹探测器的测量结果进行了比较,在±２５％的误差范围内一致     

电磁波辐射的危害性及其防护

介绍电磁波辐射对生命体的危害性、相关判据及危害作用机理。重点阐述有关防护措施。     

放射性同位素自动分装系统

研制的ＴＦ—Ａ 设备是用计算机控制的同位素自动分装系统。它由分装防护箱、机械传动、计算机自动分装和辐射剂量监测部分组成,可使γ辐射强度减弱９０％ 以上,并可隔室操作,以确保工作人员的安全和健康     

油品引燃时间的影响因素研究

以激光作为强辐射源对煤油,轻柴油和重柴油进行了直接引燃试验,研究了引燃时间受入射辐射热强度,油品性质和热辐射入射角度影响的关系。     

石油测井用中子源辐射屏蔽研究

放射源测井技术是当今石油勘探和开发中必不可少的手段，开展对测井人员的屏蔽防护研究十分必要。将聚乙（丙）烯与碳化硼和氧化铝等以不同比例混合后制成的板材和织物具有良好的热中子、中能中子和快中子屏蔽效果，加工成屏蔽装置后，可使镅－铍源中子的屏蔽率达到６２．０６％，γ射线屏蔽率达到３２．４３％，结合中子辐射防护服和防护围裙等的使用，可较好地解决测井人员的辐射防护问题。     

海洋核动力平台核事故应急监测策略研究综

综述了国外核事故应急监测策略研究进展,以及我国在核应急监测法规标准、应急监测方法、应急辐射环境监测技术等方面的研究现状,从海洋核动力平台的法规标准、应急监测方案、应急辐射监测项目和应急监测方法4个方面进行了探讨,并提出了制定核应急监测政策及标准规范、建立应急监测预案库、加快研发应急采样与监测方法、建立海洋放射性监测体系等建议。     

我国主要城市的大气质量的反演、重建与分析

该文收集有关城市的1959~1979年逐年的晴天太阳辐射资料,根据辐射传输方程扣除水汽和CO₂的吸收效应,利用各地区污染物浓度垂直分布和混合层高度规律,再同已有的TSP监测资料分区分析,可得到有关地区的大气TSP质量的逐年反演值。      

The effect of the exposure time on the value of a manSievert averted

The basis of the manSievert as a unit for collective radiation dose is discussed and previous recommendations are considered for how much should be spent to avert a collective dose of 1 manSv. New calculations are given using the J-value method. It is shown that the value to be assigned to averting a manSievert depends on the duration of averted exposure as well as on the net discount rate and the loan rate thought to be appropriate. Different figures will result depending on whether the exposed group consists of workers or the general public. The variation with dose duration is so large that it is not possible to recommend a single figure for the value of a manSievert. Instead, tables are given at two conservative, loan and net discount rates for the value of a manSievert as a function of exposure time. The base data for the J-value method need to be updated annually, and this means that the values given in the tables will increase over time as people live longer and become richer.     

Concentrations of U,U, U,Th, Th,Th, Ra,Ra, Ra,Po, Pb and Pb in drinking water in Italy: reconciling safety standards based on measurements of gross α and β

Some important naturally occurring α- and β-radionuclides in drinking water samples collected in Italy were determined and the radiological quality evaluated. The mean activity concentrations (mBq L⁻¹) of the radionuclides in the water samples were almost in the order: 26 ± 36 (²³⁴U) > 21 ± 30 (²³⁸U) > 8.9 ± 15 (²²⁶Ra) > 4.8 ± 6.3 (²²⁸Ra) > 4.0 ± 4.1 (²¹⁰Pb) > 3.2 ± 3.7 (²¹⁰Po) > 2.7 ± 1.2 (²¹²Pb) > 1.4 ± 1.8 (²²⁴Ra) > 1.1 ± 1.3 (²³⁵U) > 0.26 ± 0.39 (²²⁸Th) > 0.0023 ± 0.0009 (²³⁰Th) > 0.0013 ± 0.0006 (²³²Th). The mean estimated dose (μSv yr⁻¹) to an adult from the water intake was in this order: 2.8 ± 3.3 (²¹⁰Po) > 2.4 ± 3.2 (²²⁸Ra) > 2.1 ± 2.1 (²¹⁰Pb) > 1.8 ± 3.1 (²²⁶Ra) > 0.94 ± 1.30 (²³⁴U) > 0.70 ± 0.98 (²³⁸U) > 0.069 ± 0.087 (²²⁴Ra) > 0.036 ± 0.044 (²³⁵U) > 0.014 ± 0.021 (²²⁸Th) > 0.012 ± 0.005 (²¹²Pb) > 0.00035 ± 0.00029 (²³⁰Th) > 0.00022 ± 0.00009 (²³²Th). It is obvious that ²¹⁰Po, ²²⁸Ra, ²¹⁰Pb and ²²⁶Ra are the most important dose contributors in the drinking water intake. As far as the seventeen brands of analysed drinking water were concerned, the committed effective doses were in the range of 2.81–38.5 μSv yr⁻¹, all well below the reference level of the committed effective dose (100 μSv yr⁻¹) recommended by the WHO. These data throw some light on the scale of the radiological impact on the public from some naturally occurring radionuclides in drinking water, and can also serve as a comparison for the dose contribution from artificial radionuclides released to the environment as a result of human practices. Based on the radionuclide composition in the analysed waters, comment was made on the new screening level for gross α activity in guidelines for drinking-water quality recommended by the WHO, 2004.     

A model for radiological consequences of nuclear power plant operational atmospheric releases

A dynamic dose and risk assessment model is developed to estimate radiological consequences of atmospheric emissions from nuclear power plants. Internal exposure via inhalation and ingestion, external exposure from clouds and radioactivity deposited on the ground are included in the model. The model allows to simulate interregional moves of people and multi-location food supply in the computational domain. Any long-range atmospheric dispersion model which yields radionuclide concentrations in air and on the ground at predetermined time intervals can easily be integrated into the model. The software developed is validated against radionuclide concentrations measured in different environmental media and dose values estimated after the Chernobyl accident. Results obtained using the model compare well with dose estimates and activities measured in foodstuffs and feedstuffs.