广东核电站事故场外应急辐射测量比对

本文主要介绍了1998－1999年粤港地区“广东核电站事故场外应急辐射测量比较”的方法和结果。辐射测量比对项目包括环境贯穿辐射剂量率，辐射累积剂量和水与食品样品中γ放射性核素含量。文中还分析和讨论了测量比对中存在的问题。     

文献题录

Radiation Protection Dosi metry Vol.106 No.1 2003讣告:Michae Bender(1929~2003)E P Goldfinchi等编者的话:辐射探测仪表与辐射测量仪表J C McDonald论航空LiF:Mg,Ti热释光剂量计的应用:综述YS Horowitz等荷兰空勤人员的剂量评价J WE Van DijkLiF热释光剂量计对能量范围在30 kVX射线-60Coγ射线之间的光子束的响应S D Davis人外周血淋巴细胞中胞质分裂阻滞诱发微核的剂量率效应NNBhat等吸入氧化钛后的人体生物动力学D Newton从静脉注射59FeCl3或57CoCl3对胎儿或母亲器官的剂量MSaunders等东京空调办公大楼中氡及其子…     

大亚湾核电站环境辐射连续监测网络系统

广东大亚湾核电站环境辐射连续监测系统于１９９３年电站装料前投入运行。１９９６年对γ辐射监没站探测器的测量几何条件和系统的避雷保护作了改进。本文主要介绍改造后系统的网络结构,软件结构,γ辐射实时监测及处理的方法。     

热释光断代的进展

本文评述了热释光断代的近况。它们是:磷光体的热释光性质;关于发光中心;辐射剂量学,综述了五种测定年辐射剂量的方法,同时也讨论另两种测定氡逸散的方法;各种不同类型标本中累积辐射剂量的测定;热释光测量中的样品制备;辐射源及校正及其在热释光断代中的应用;测量热释光的装置。     

大亚湾地区三次环境γ辐射剂量率调查测量结果比较分析

由于相继建设广东大亚湾核电站(GNPS)和岭澳核电站(LAPS)，大亚湾地区自1988年至2000年先后进行了三次环境γ辐射剂量率调查。比较分析三次测量结果，大亚湾地区原野和室内的γ辐射水平总体上保持不变，道路的γ辐射水平则略有上升。本文还分析了不同时间特定区域γ辐射水平调查结果差异的原因，说明在环境γ辐射剂量率测量中，测点的代表性直接影响测量结果的可比性。     

新型低能辐射远程测量系统设计

为了实现低能辐射精确的远程测量,设计了一种基于ARM单片机和ZigBee无线传输的新型低能辐射远程测量系统,优化了前端算法,提出了精度更高的整体求和算法。系统可靠性利用ARM单片机发射数据与ZigBee接收数据的一致程度来测试,算法精确度利用MATLAB进行图像处理,再计算辐射亮点灰度值,并用插值拟合方法进行数据处理来测试。实验结果表明,整体求和算法的运用以及ARM和ZigBee的结合可实现低能辐射精确的远程测量。     

混合辐射场测量中屏蔽设计的组合优化方法

在混合辐射场测量中，各测点的辐射环境和测量目标不同，同一种屏蔽方案不能很好地满足各测点的需要。有必要发展一种辐射屏蔽自动优化设计方法，实现屏蔽效果的定量评价，并针对不同情况进行屏蔽优化。根据代价利益分析方法提出了辐射屏蔽措施的优化评估方法；引入遗传算法建立了组合屏蔽自动设计方法。计算表明该评价方法与文献及MCNP模拟计算结果相符；在典型的裂变中子、裂变r混合辐射条件下，优化设计方案的辐射干扰相当于原方案的44％。组合屏蔽设计方法可以针对特定辐射环境和测点参数进行自动优化设计，对混合辐射场测量的方案设计和数据分析具有积极的作用。     

青岛市环境微波辐射的测量分析与卫生学评价

本文从环境保护的目的出发,论述了青岛市已建、拟建大型电磁辐射体环境微波辐射的测量理论、测量技术及计算方法。根据测量计算结果并参照微波辐射的公众安全限值,对辐射体在环境空间的微波辐射对公众的影响作出卫生学评价。     

土壤中^90Sr和生物灰中^137Cs测量比对

介绍了浙江省辐射环境监测站组织实施的2009年全国辐射环境监测系统土壤中^90Sr和生物灰中^137Cs测量比对情况及其结果分析。比对结果表明,90%的测量值为满意结果,5%的测量值为有问题结果,5%的测量值为离群值。通过此次比对,基本上了解了全国辐射环境监测系统土壤中^90Sr和生物灰中^137Cs测量水平,为今后进一步开展系统内的质保工作提供了依据。     

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。     

五省(市)环境陆地γ辐射水平调查中所用仪器的比对结果

本文报道了对五省市环境陆地γ辐射水平调查中所用仪器的刻度和比对情况。对离地1m 高处陆地γ辐射空气吸收剂量率,SG-102型和 FT-620型闪烁照射量率仪的测量值与高压电离室符合得很好,两次比对的平均比值分别为1.01和1.02。对密云水库水面的宇宙射线空气吸收剂量率,SG—102型仪器的响应为高压电离室的89—110%,FT—620型仪的响应为高压电离室的47—84%,两次比对的平均值分别为60%和64%;故在测量中扣除宇宙射线贡献时,应作修正。     

基于蒙特卡罗方法的航空机组人员辐射剂量评估北大核心CSCD

采用辐射仿真人体面元模型和数字化飞机模型,基于蒙特卡罗方法开展了航空机组人员的航空辐射剂量研究。选取昆明至北京航线为例,评估了航空机组人员在该航线飞行时受到的航空辐射有效剂量率,分析了人体参数对航空辐射有效剂量率的影响,并探索了航线参数变化时机组人员受到的航空辐射有效剂量率的变化。结果表明,机组人员在昆明至北京航线受到的航空辐射有效剂量率为2.114μSv/h,基于中国人参考生理特征的体模和高加索人体参数体模的有效剂量率评估结果差异为25.3%;航线参数中航线的高度是最主要的影响因素,14 km飞行高度的航空辐射有效剂量率达到10 km高度时的1.8倍,同时,航线纬度升高时,机组人员受到的航空辐射有效剂量率也会产生显著的提升。该研究对航空机组人员的辐射剂量评估具有一定的参考和指导意义。     

Space radiation dosimetry in low-Earth orbit and beyond

Space radiation dosimetry presents one of the greatest challenges in the discipline of radiation protection. This is a result of both the highly complex nature of the radiation fields encountered in low-Earth orbit (LEO) and interplanetary space and of the constraints imposed by spaceflight on instrument design. This paper reviews the sources and composition of the space radiation environment in LEO as well as beyond the Earth's magnetosphere. A review of much of the dosimetric data that have been gathered over the last four decades of human space flight is presented. The different factors affecting the radiation exposures of astronauts and cosmonauts aboard the International Space Station (ISS) are emphasized. Measurements made aboard the Mir Orbital Station have highlighted the importance of both secondary particle production within the structure of spacecraft and the effect of shielding on both crew dose and dose equivalent. Roughly half the dose on ISS is expected to come from trapped protons and half from galactic cosmic rays (GCRs). The dearth of neutron measurements aboard LEO spacecraft and the difficulty inherent in making such measurements have led to large uncertainties in estimates of the neutron contribution to total dose equivalent. Except for a limited number of measurements made aboard the Apollo lunar missions, no crew dosimetry has been conducted beyond the Earth's magnetosphere. At the present time we are forced to rely on model-based estimates of crew dose and dose equivalent when planning for interplanetary missions, such as a mission to Mars. While space crews in LEO are unlikely to exceed the exposure limits recommended by such groups as the NCRP, dose equivalents of the same order as the recommended limits are likely over the course of a human mission to Mars.     

"辐射防护体系演进"中一些问题的讨论

从中国辐射防护的实践看，现行辐射防护体系进行适当简化和更加协调一致是必要的。仅仅基于保护人的防护举措不是在各种情况下均能满足环境的要求。辐射防护的含意应该包括保护环境免受电离辐射的影响。集体剂量是一个有用的但需要明确其应用范围的指标。它的应用有利于促进辐射防护水平的提高，但应明确其应用的条件，如时间和空间等。天然辐射是人类所受照射的最大来源。有必要控制天然辐射产生的职业照射，如地下矿工和航空机组人员。加强控制人工辐射和天然辐射对孕妇和儿童的照射是重要的，其中特别是放射诊断和治疗。     

大型核动力船舶船员剂量评价体系研究

建立船员的剂量评价体系是实现我国核动力商船等发展规划亟待解决的关键技术之一。对船员人数最多、人员编制最复杂和辐射防护涉及面最广的大型核动力船舶开展了研究，提出了大型核动力船舶船员剂量评价体系。该剂量评价体系参照国际辐射防护委员会和国际原子能机构推荐的方法建立，包括基本剂量量、剂量限值和参考水平以及剂量计算和监测3大块，覆盖计划照射和潜在照射2种情况，能够满足前瞻性、实际性和回顾性全部3个阶段的船员剂量评价需求。另外，该剂量评价体系还给出了船员剂量评价的具体方法，如需考虑的辐射源和照射途径，应使用的模型、量和取值等。      

γ辐射剂量率仪对宇宙射线响应及校准因子的间接校准

通过已测定和未测定宇宙射线响应的γ辐射测量仪在天然环境辐射场中的比对测量,可以确定辐射测量仪的宇宙射线响应及校准因子。选择美国通用电器公司生产的高压电离室RSS-131环境辐射监测仪作为量值传递仪器,对BH3103B便携式X-γ剂量率仪和6150闪烁体探测器γ辐射测量仪进行宇宙射线响应和校准因子的间接校准,与广东省辐射剂量计量检定站所检定的结果比较,校准因子的相对偏差分别为-2%和0;与在万绿湖对宇宙射线空气吸收剂量率的实测值比较,宇宙射线响应的相对偏差分别为-3.6%和3.1%。结果基本一致。     

陨石的自然热释光与母体的宇宙射线辐照演化历史

研究了一组近年收集到的地球年龄〈３０ａ的中国普通球粒陨石的自然热释光及其宇宙成因核素数据，发现长宇宙射线暴年龄的陨石具有更小的近日距，与它们相似的轨道演化有关。在最后５０Ｍａ中，普通球粒陨石母体的轨道经历了从１．０ＡＵ到０．９ＡＵ的演化。暴露期间经历了太阳加热的母体较正常母体具有稍低的自然热释光值，宇宙暴露前的加热事件对自然热释光值的影响更大。     

全国辐射环境监测网络环境γ辐射剂量率测量比对

2013年12月,环境保护部辐射环境监测技术中心在四川省凉山彝族自治州组织了全国辐射监测网络的环境γ辐射剂量率和宇宙射线响应测量比对。共有32家成员单位的47台仪器设备参与了7个环境测点的比对测量,比对结果统一到γ空气吸收剂量率,采用Z比分数值分别对不同型号仪器的测量结果进行评价。比对结果显示,闪烁计数器测量数据的离散性较高压电离室大。除宇宙射线响应测点外,两类仪器的测量结果保持着较好的线性。     

A Screening Model for Calculating the Risks of Transporting High Level Radioactive Waste

Abstract

In transporting high level radioactive waste (including spent nuclear fuel), shippers (and sometimes carriers) need to evaluate the risks of potential radiation exposure to the public and transport workers. A simple model is presented that can be applied to nuclear waste transport risk assessments. The model considers radiation risks arising from incident free exposure, accidental release-caused exposure to on-link population, off-link population, crew, transport workers, etc. Important parameters and factors that affect the radiation dose level are grouped using the physics of the different exposure phenomena. The total radiation risk (in person-rems) is given by a linear combination of the groups of these factors, each representing a different type of exposure. The radiation exposure risk assessment is reduced to the evaluation of a single linear algebraic equation containing five distinct terms and each term containing the groups of parameters and a constant coefficient. The estimation of the values of the constant coefficients was accomplished by selecting a sample of 65 origin-destination (0-D) pairs and simulating the shipment of high level nuclear waste or spent nuclear fuel between each O-D pair, and evaluating the radiation dose risks to each group of population. RADTRAN 4 was used in the detailed assessments. The coefficient values were tested for statistical robustness using a sampling hypothesis and t-statistics. These values are presented. The simplified model presented here represents a viable and economical option as a radiological risk assessment tool, to be used in mode or route options screening.     

Scope of radiological protection control measures

In this report, the Commission recommends approaches to national authorities for their definition of the scope of radiological protection control measures through regulations, by using its principles of justification and optimisation. The report provides advice for deciding the radiation exposure situations that should be covered by the relevant regulations because their regulatory control can be justified, and, conversely, those that may be considered for exclusion from the regulations because their regulatory control is deemed to be unamenable and unjustified. It also provides advice on the situations resulting from regulated circumstances but which may be considered by regulators for exemption from complying with specific requirements because the application of these requirements is unwarranted and exemption is the optimum option. Thus, the report describes exclusion criteria for defining the scope of radiological protection regulations, exemption criteria for planned exposure situations, and the application of these concepts in emergency exposure situations and in existing exposure situations. The report also addresses specific exposure situations such as exposure to low-energy or low-intensity adventitious radiation, cosmic radiation, naturally occurring radioactive materials, radon, commodities, and low-level radioactive waste. The quantitative criteria in the report are intended only as generic suggestions to regulators for defining the regulatory scope, in the understanding that the definitive boundaries for establishing the situations that can be or need to be regulated will depend on national approaches.