Estimation of thyroid doses and health risks resulting from the intake of radioactive iodine in foods and drinking water by the citizens of Tokyo after the Fukushima nuclear accident

The release of radioactive materials from the Fukushima nuclear power plant after the Great East Japan Earthquake on 11 March 2011 poses health risks. In this study, the intake of iodine 131 (I-131) in drinking water and foods (milk, dairy products, and vegetables) by citizens of Tokyo was estimated. The effects of countermeasures (restrictions on the distribution of foods and the distribution of bottled water for infants) on reducing intake were also evaluated. The average thyroid equivalent doses without countermeasures from 21 March 2011 were 0.42 mSv in adults, 1.49 mSv in children, and 2.08 mSv in infants. Those with countermeasures were 0.28, 0.97, and 1.14 mSv respectively, reductions of 33%, 35%, and 45%. Drinking water contributed more to intake by adults and children than foods. The intake of I-131 within the first 2 weeks was more than 80% of the estimated intake, owing to its short half-life, indicating that rapid countermeasures are important in reducing intake. The average risks of cancer incidence and mortality due to I-131 for infants were estimated to be 3 × 10⁻⁵ and 0.2 × 10⁻⁵, respectively, lower than the annual risks of traffic accidents, naturally occurring radioactive material (potassium 40), and environmental pollutants such as diesel exhaust particles.     

The structure of the fire fighting foam surfactant Forafac®1157 and its biological and photolytic transformation products

For several decades, perfluorooctane sulfonate (PFOS) has widely been used as a fluorinated surfactant in aqueous film forming foams used as hydrocarbon fuel fire extinguishers. Due to concerns regarding its environmental persistence and toxicological effects, PFOS has recently been replaced by novel fluorinated surfactants such as Forafac®1157, developed by the DuPont company. The major component of Forafac®1157 is a 6:2 fluorotelomer sulfonamide alkylbetaine (6:2 FTAB), and a link between the trade name and the exact chemical structure is presented here to the scientific community for the first time. In the present work, the structure of the 6:2 FTAB was elucidated by ¹H, ¹³C and ¹⁹F nuclear magnetic resonance spectroscopy and high-resolution mass spectrometry. Moreover, its major metabolites from blue mussel (Mytilus edulis) and turbot (Scophthalmus maximus) and its photolytic transformation products were identified. Contrary to what has earlier been observed for PFOS, the 6:2 FTAB was extensively metabolized by blue mussel and turbot exposed to Forafac®1157. The major metabolite was a deacetylated betaine species, from which mono- and di-demethylated metabolites also were formed. Another abundant metabolite was the 6:2 fluorotelomer sulfonamide. In another experiment, Forafac®1157 was subjected to UV-light induced photolysis. The experimental conditions aimed to simulate Arctic conditions and the deacetylated species was again the primary transformation product of 6:2 FTAB. A 6:2 fluorotelomer sulfonamide was also formed along with a non-identified transformation product. The environmental presence of most of the metabolites and transformation products was qualitatively demonstrated by analysis of soil samples taken in close proximity to an airport fire training facility.     

Toxicological characterization of the landfill leachate prior/after chemical and electrochemical treatment: A study on human and plant cells

In this research, toxicological safety of two newly developed methods for the treatment of landfill leachate from the Piškornica (Croatia) sanitary landfill was investigated. Chemical treatment procedure combined chemical precipitation with CaO followed by coagulation with ferric chloride and final adsorption by clinoptilolite. Electrochemical treatment approach included pretreatment with ozone followed by electrooxidation/electrocoagulation and final polishing by microwave irradiation. Cell viability of untreated/treated landfill leachate was examined using fluorescence microscopy. Cytotoxic effect of the original leachate was obtained for both exposure periods (4 and 24 h) while treated samples showed no cytotoxic effect even after prolonged exposure time. The potential DNA damage of the untreated/treated landfill leachate was evaluated by the comet assay and cytokinesis-block micronucleus (CBMN) assay using either human or plant cells. The original leachate exhibited significantly higher comet assay parameters compared to negative control after 24 h exposure. On the contrary, there was no significant difference between negative control and chemically/electrochemically treated leachate for any of the parameters tested. There was also no significant increase in either CBMN assay parameter compared to the negative control following the exposure of the lymphocytes to the chemically or electrochemically treated landfill leachate for both exposure periods while the original sample showed significantly higher number of micronuclei, nucleoplasmic bridges and nuclear buds for both exposure times. Results suggest that both methods are suitable for the treatment of such complex waste effluent due to high removal efficiency of all measured parameters and toxicological safety of the treated effluent.     

Long-term geochemical evolution of the near field repository: insights from reactive transport modelling and experimental evidences

The KBS-3 underground nuclear waste repository concept designed by the Swedish Nuclear Fuel and Waste Management Co. (SKB) includes a bentonite buffer barrier surrounding the copper canisters and the iron insert where spent nuclear fuel will be placed. Bentonite is also part of the backfill material used to seal the access and deposition tunnels of the repository. The bentonite barrier has three main safety functions: to ensure the physical stability of the canister, to retard the intrusion of groundwater to the canisters, and in case of canister failure, to retard the migration of radionuclides to the geosphere. Laboratory experiments (< 10 years long) have provided evidence of the control exerted by accessory minerals and clay surfaces on the pore water chemistry. The evolution of the pore water chemistry will be a primordial factor on the long-term stability of the bentonite barrier, which is a key issue in the safety assessments of the KBS-3 concept.In this work we aim to study the long-term geochemical evolution of bentonite and its pore water in the evolving geochemical environment due to climate change. In order to do this, reactive transport simulations are used to predict the interaction between groundwater and bentonite which is simulated following two different pathways: (1) groundwater flow through the backfill in the deposition tunnels, eventually reaching the top of the deposition hole, and (2) direct connection between groundwater and bentonite rings through fractures in the granite crosscutting the deposition hole. The influence of changes in climate has been tested using three different waters interacting with the bentonite: present-day groundwater, water derived from ice melting, and deep-seated brine. Two commercial bentonites have been considered as buffer material, MX-80 and Deponit CA-N, and one natural clay (Friedland type) for the backfill. They show differences in the composition of the exchangeable cations and in the accessory mineral content. Results from the simulations indicate that pore water chemistry is controlled by the equilibrium with the accessory minerals, especially carbonates. pH is buffered by precipitation/dissolution of calcite and dolomite, when present. The equilibrium of these minerals is deeply influenced by gypsum dissolution and cation exchange reactions in the smectite interlayer. If carbonate minerals are initially absent in bentonite, pH is then controlled by surface acidity reactions in the hydroxyl groups at the edge sites of the clay fraction, although its buffering capacity is not as strong as the equilibrium with carbonate minerals. The redox capacity of the bentonite pore water system is mainly controlled by Fe(II)-bearing minerals (pyrite and siderite). Changes in the groundwater composition lead to variations in the cation exchange occupancy, and dissolution–precipitation of carbonate minerals and gypsum. The most significant changes in the evolution of the system are predicted when ice-melting water, which is highly diluted and alkaline, enters into the system. In this case, the dissolution of carbonate minerals is enhanced, increasing pH in the bentonite pore water. Moreover, a rapid change in the population of exchange sites in the smectite is expected due to the replacement of Na for Ca.     

内抽外压式集尘器实验、数值模拟与分析

根据内抽外压式集烟尘器专利研制了一个内抽外压式集尘器,并在井下进行实验。经过3种方法测试均收到预期的的效果,司机工作区达到了国家卫生要求,由于采用外筒压风,防止了瓦斯积聚避免瓦斯爆炸。应用离散颗粒模型模拟了内抽外压式集尘器内气相流场和粉尘颗粒的运动,该集尘器不仅把矿井巷道中细微可呼吸粉尘吸收到除尘器中,又能防止了瓦斯积聚。数值模拟与实验结果的一致性表明:把内抽外压式集尘器放置在掘进机前方,由于粉尘在气流的携带下运动使掘进机司机在矿井巷道中的工作环境得到改善,减少矿工患尘肺病的概率,开发了井下集尘的新工艺、新设备。     

安全评价方法在危险废物处置环境风险评价中的应用探讨

对安全评价方法在危险废物处置建设项目环境风险评价中的运用进行初步探索。主要用"工艺过程风险因素分析表"对工艺过程潜在风险性识别;用蒙德法进行源项分析;用池火灾模型、蒸气云爆炸伤害模型对易燃、易爆物质的火灾、爆炸等重大事故后果进行计算,得出人员的伤亡半径和财产损失半径等参数,以便于判断风险的可接受水平。分析结果表明:采用安全评价方法对危险废物处置建设项目进行环境风险评价是适用的、可行的。     

北京核与辐射恐怖事件风险分析

采用风险分类-要素分析-风险排序的思路,对北京市核与辐射恐怖事件风险进行分析。根据国际上1998—2006年该类恐怖事件的实例,从事件所涉及的材料、场所角度将核与辐射恐怖事件分为6大类。结合北京市的实际情况进行涉核恐怖事件的要素分析,将北京市各类场所划分为4类敏感区并与5类涉核恐怖事件结合起来,得到北京市核与辐射恐怖事件风险构成图。通过风险分析,笔者认为北京市发生核与辐射恐怖事件风险最大的场所为核研究机构,最容易发生的核与辐射恐怖事件类型为涉及放射源的恐怖事件,结合分析结果对从阻止、探测、响应3个层次上提出了奥运核安保工作的反核恐工作建议。     

矿井瓦斯煤尘爆炸传播数值模拟研究

基于连续相、燃烧、颗粒相数理方程建立瓦斯煤尘爆炸传播数理模型,并应用连续相、颗粒相计算方法,依据大型巷道瓦斯爆炸、瓦斯煤尘爆炸传播实验数据,借助普遍应用的流场模拟平台,成功开发瓦斯、煤尘爆炸数值模拟系统。该系统可有效地模拟煤矿瓦斯、煤尘的爆炸事故过程,对瓦斯爆炸的爆燃转爆轰、煤尘是否参与爆炸、爆炸冲击传播速度、衰减规律以及爆炸灾害的波及范围都能进行较准确的模拟。     

隔爆型电机在火炸药危险场所应用的安全性分析

针对普通隔爆型电机应用于火炸药粉尘危险场所的安全性问题进行定量分析,设计壳体粉尘侵入量试验,系统研究不同间隙下的粉尘侵入量,根据试验数据,应用曲线外推法及阿贝尔(Abel)余容状态方程计算爆压,结合材料力学及薄壁理论进行隔爆型电气设备外壳强度及刚度的校核。计算表明:若壳体内粉尘较均匀的悬浮在空中,切向应力与许用应力处于同一数量级;如果火炸药粉尘在轴承室、接线盒等局部堆积成火炸药层,切向应力比许用应力大两个数量级。试验结果强调:用于火炸药粉尘危险场所的电气设备必须有特殊的防爆结构设计,普通的隔爆电机用于火炸药粉尘危险环境时存在一定的安全隐患。     

HAN阻隔防爆模型研究

通过合理简化,利用多方气体状态方程,分别建立油品储运容器内可燃混合气体定容爆炸模型和装设阻隔防爆材料的油品储运容器内可燃混合气体爆炸模型,获得了阻隔防爆性能测试装置的燃爆容器抗爆设计限值,以及其在HAN阻隔防爆测试中燃爆容器试爆压力量级的控制下限值,同时,还给出HAN工程应用中容器留空率的计算方法,具有实际指导意义。