新疆辐射环境监理站顺利收贮了三个报废的放射源

新疆维吾尔自治区肿瘤医院的一个艳一137治疗源和两个镭一226校验源因故报废，向新疆辐射环境监理站提出送贮的申请。根据这3个放射源未达到有效屏蔽的具体情况，双方共同商定了屏蔽方案，设计并定做了屏蔽体，达到了收贮的要求。1997年11月生日，双方组织了精干的人员，对废放射源进行了认真包装和监测，按照国家环保局的有关规定和操作要求，顺利地将3个废放射源收贮到新疆城市放射性废物库。这3个废放射源的收贮，得到有关方面和群众的好评，保护了环境，安定了人心。新疆辐射环境监理站顺利收贮了三个报废的放射源@刘鄂$新疆辐射环境监…     

模拟徒步环境中放射源搜寻与搜寻人员受照剂量估算

模拟环境中位置未知放射源的搜寻过程、使用仪表和搜寻人员受照剂量估算，对丢失、被盗等在役与退役放射源搜寻有指导意义。     

放射源管理体制的改革

随着核技术应用领域的逐步扩展、放射源数量的增多及辐射事故突发频率的提高，2003年《中华人民共和国放射性污染防治法》发布并实施，该法明确了环境保护行政主管部门对放射源实行统一监督管理的职能。此项职能移交，逐步解决了放射源多家管理存在的问题和隐患，理顺了放射源监管体系，使我国放射源监管水平有望趋于国际化。     

基于自动监测监控技术的环境安全防控系统的设计与应用

采用先进的物联网、云计算和模型仿真等技术，陈述了基于自动监测监控技术的环境安全防控系统的设计和应用。该系统利用物联网、GIS等先进技术，将重点源企业、河流断面、放射源等纳入到统一的环境监控网络中，全方位构建区域内环境安全防控大格局。根据城市环境应急现状，建立三级环境安全防控体系，实现对环境安全事故的有效预防、控制和处置。     

放射源远程自动监控管理体系的构建

以苏州的若干家放射源使用单位为例,从点位源的剂量监测、视频监控、红外报警、数据传输等方面出发,围绕提高放射源自动监控这一主题,展开了放射源远程自动监控体系的探索.     

邻苯二甲酸二正辛酯的气相色谱测定

气相色谱电子捕获检测器测定工业设施验收中的邻苯二甲酸二正辛酯是一种灵敏度高的有效方法，但检测器的放射源极易受污染县很难清洗。改用氢火焰检测器测定则其灵敏度较低，无法分析仪浓度的环境样品，今 根据邻 苯二甲酸二正辛酯２的高低分别选用氢火焰检测器和电子捕获检测顺进行测定，方法实用可行。     

保障辐射环境安全的放射源在线监控管理系统

利用集固定源及移动源等自动监控仪器和移动GPRS监控数据的采集、传输、存储、展示、统计及应用的综合业务平台,通过环保系统内部的业务协同,有效地获取放射源动态业务信息,可以提高核与辐射环境监管工作的信息化水平和对辐射污染事件的快速反应能力,为核与辐射环境管理提供服务.     

高风险移动放射源风险管控模糊综合评价

根据高风险移动放射源辐射安全风险特点与辐射事故经验反馈,结合辐射安全监管部门和企业实际,在充分调研的基础上,构建高风险移动放射源辐射安全风险管控评价指标体系,体系分为目标层、准则层和方案层,准则层8项指标,方案层40项指标。采用层次分析法确定各指标权重,运用模糊综合评价方法对甘肃省7家高风险移动放射源企业进行评价,结果表明决策层指标权重较大,与实际情况相符。     

江苏省高风险移动放射源在线监管系统设计

为了满足国家有关高风险移动源监管工作要求,研制了具备全球定位系统(GPS)、无线射频识别、辐射剂量监控功能的监控终端硬件,并开发设计了高风险移动源实时监控系统软件平台。对该系统平台软件和监控终端的功能及应用情况进行了分析,针对监控终端结构设计、续航时间较短、耐用性较差、野外信号弱等问题提出后续改进建议。该监控系统可以有效实现高风险移动放射源的动态监控,进一步提升江苏省高风险移动放射源的监管技术水平。     

2016—2021年四川省城市放射性废物库库区辐射环境监测

为提高四川省城市放射性废物库的安全管理水平,确保库区辐射环境安全和库内放射源实体安全,对2016—2021年四川省城市放射性废物库的库区环境监测结果进行了分析。分析表明：库区的γ辐射剂量率满足《核技术利用放射性废物贮存库选址、设计与建造技术要求》(试行)的要求,库区表面污染水平满足《电离辐射防护与辐射源安全基本标准》(GB 18871—2002)的规定,库区气溶胶历年监测数据一致性较好。此外,库区完善的安防措施为库区的安全运行提供了有力保障。四川省城市放射性废物库的运行未对库区环境造成不良影响,库区辐射环境质量良好。废物库的运行状态良好,库区辐射安全可控,其安全运行对保障全省核技术利用产业的发展和辐射环境的安全起到了重要作用。     

同位素技术在环境科学研究中的应用进展

综述了近年来同位素技术在国内外环境科学研究中的应用状况,简要介绍了同位素技术的应用原理与分析方法。总结了放射性同位素技术和稳定同位素技术在环境史重建、污染物示踪及源解析等方面的应用,重点介绍了稳定同位素技术在水、大气和土壤污染物源解析中的应用进展。对未来同位素技术在环境科学研究中的应用进行了展望,提出了多种同位素联合解析、建立和完善定量源解析模型等建议。     

太湖流域稀土企业放射性废水污染调查

为治理太湖流域稀土加工过程中产生的放射性废水环境污染,对比分析了太湖流域2家典型稀土企业2005年-2009年的废水和底泥的总α、总β和238U、232Th、226Ra、40K,评价放射性污染对环境的影响程度,为消除放射性废水环境污染危害提供客观依据和方法建议.     

Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces

We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.     

Environmental Exposure Assessment for Emergency Response in a Nuclear Power Plant Using an Integrated Source Term and 3D Numerical Model

Nuclear power plants are normally assumed to be safe when their radiation impact in all operational states is kept at a reasonably low level. However, accidentally released radioactive substances and ionizing radiation may lead to a situation that cannot maintain the regulatory prescribed dose limits for internal and external exposure of the personnel and population. Nuclear emergency preparedness and response in nuclear or radiological events have been of concern recently in international communities. Nuclear power plants may need to provide essential information regarding possible scenarios of accidental releases that might have short-term detrimental effects and long-term risks in nearby populated regions. This paper presents a synergistic integration of a source term model and a three-dimensional, time-dependent, numerical model (i.e., HOTMAC/RAPTAD), which was applied to simulate a specific scenario in which a vapor cloud was accidentally released from Maanshan (i.e., the third nuclear power plant) in South Taiwan. It aims at dealing with middle-range risk assessment for nuclear emergency preparedness and response. The solutions of such an integrated modeling platform can be found with numerical analyses that describe the processes of radionuclide generation, transport, decay, and deposition, giving the final risk assessment in a neighboring coastal city—Kaohsiung, South Taiwan. In addition, sensitivity analyses were performed to evaluate the internal consistency of model parameters, which further support the application potentials. Such a modeling technique is valuable because it can characterize the fate and transport of radioactive nuclides over the long term. The case study in South Taiwan uniquely demonstrates the feasibility and significance of such model integration.     

Radioactive Contamination Control by Atmospheric Dispersion Assessment of Airborne Indicator Contaminants: Numerical Model Validation

In this work, a numerical model is proposed to estimate air concentration of released airborne radioactive contaminants ¹³¹I and ¹³⁷Cs. A Gaussian dispersion model is used to assess the atmospheric dispersion of radioactive contaminants released continuously from a nuclear power plant as a result of an accident. The model uses various input parameters such as source height, release rate, stability class, wind speed, and wind direction. The validation of the model was carried out by comparing its predicted values with published experimental data. The model was extensively tested by simulating several accidental situations. The main conclusion drawn from these tests is that for large downwind distances from the release point, the contaminant concentrations predicted by the model diverge drastically from measured data, while for short distances, the predicted values generally agree quite well with experimental data. The obtained activity concentrations range from 1.57?×?10² to 6.43?×?10³ Bq/m³ for ¹³¹I and from 3.18?×?10^?2 to 9.72?×?10² Bq/m³ for ¹³⁷Cs. The estimated standard deviation coefficients values range of 7.2 to 6847.7 m, and the maximum absolute error predicted by the model for these parameters was less than 5%.