Mapping of tritium emissions using absorption vapour samplers

Püspökszilágy Radioactive Waste Treatment and Disposal Facility (RWTDF) is a typical near-surface engineered repository designated to store low- and intermediate-level wastes from various institutes, research facilities and hospitals in Hungary. Two automatic combined ¹⁴C–tritium sampling units installed at the facility sample the air 2 m above surface. The one installed near the vaults detects tritium (T) activities two orders of magnitude higher than the far reference sampling unit. To localize the T emissions, 19 small absorption vapour samplers filled with silica gel were settled onto the ground surface. After the saturation of the silica gel, the water was recovered and its T concentration was measured with a low-background liquid scintillation counter. The absorption vapour samplers are cheap, simple and easy-to-use. We present the samplers and the T distribution map constructed from the data, which helps to localize the T emission.     

倒计时信号灯绿灯间隔时间设置研究

就保障倒计时信号交叉口交通安全而言,适当设置倒计时信号灯绿灯间隔时间具有重要意义.选择南京一个道路交叉口,利用交通冲突理论,分析产生严重交通冲突的条件,考虑车流不饱和与饱和2种情况,得到在不发生严重交通冲突条件下的绿灯间隔时间,并通过实例说明.研究结果显示,在车流饱和状态下,头车与尾车均为大车时,头车以初速度零开始加速进入交叉口时绿灯间隔时间应最短;在不饱和状态下,头车与尾车均为大车时,头车以一定速度通过交叉口时绿灯间隔时间应最长;车流饱和时绿灯间隔时间应较短,车流不饱和时绿灯设置间隔时间应较长.     

基于视频分析的人群密集场所客流监控预警研究

为实现人群密集场所客流安全隐患早发现,辅助管理人员早决策,人群聚集风险区早疏散,提升对灾难的预见性和主动性。在国内外人群异常聚集监测预警现状分析基础上,对比分析得出监控视频分析技术是解决人群密集场所精准预警难题较为理想的解决方案;构建以视频智能分析的人群计数、密度估计、行人追踪、活动烈度识别为核心技术的人群密集场所风险预警技术框架;将该技术框架应用到某大型商圈的商业街区,获得监控区域内的人群总数、密度分布、行人轨迹和异常活动等特征。结果表明:提出的基于视频分析的人群密集场所风险预警技术框架可为城市大型商圈、交通枢纽、大型活动场所等城市公共场所的安全管理提供参考和借鉴。     

电子产品野外环境下温循加速载荷谱编制方法

目的 将电子产品在野外环境下日变化波动与季节差异明显的温度载荷编制成温循载荷谱和转换为加速载荷谱.方法 通过四点雨流计数法提取原谱中的载荷循环信息,对提取的循环信息进行分布拟合、相关性检验等统计分析,进而构建循环均值与范围值的联合概率密度函数,再运用概率密度法,编制出 8×8 二维环境载荷谱.在二维载荷谱基础上,编制出温循载荷谱,使用针对电子部件参数修正的加速方程转化为加速载荷谱.结果 利用野外作业现场1个作业周期内的气温纪录,提供了一套编制温循载荷谱和转换加速载荷谱的合理化流程和解决方案.结论 该制谱方法可以利用原始环境谱中绝大部分有效信息,较好地还原电子部件野外作业阶段经历的温度变化过程,为电子产品的加速寿命试验和使用寿命预测奠定基础.     

基于频域分析的机载液压驱动装置疲劳寿命预测方法研究

目的 采用时域雨流法和4 种频域振动疲劳分析方法对机载液压驱动装置的危险部位进行寿命预测及频域方法适用性研究.方法 首先通过有限元随机振动分析得到该结构耳片危险区域的应力PSD,计算的谱宽系数都集中在 0.3～0.35,是窄带和宽带分界区域.然后运用4种典型的载荷谱估计模型,即三区间法、基于Dirlik雨流幅值经验模型、用于窄带过程的Rayleigh分布模型、Weibull分布模型,得到危险位置的疲劳寿命安全系数.接着将应力PSD映射为应力-时间序列,并基于雨流计数法得到疲劳寿命安全系数.最后以时域疲劳预测结果基准,对 4 种频域方法的适用性进行讨论.结果 预测结果显示,Dirlik方法预测的 9 个安全系数最为可靠,Rayleigh 法结果一般,三区间法和 Weibull 法最差.结论 在窄带和宽带分界区域的谱宽系数,建议采用Dirlik方法,不建议采用三区间法和Weibull法.     

Experimental investigation and modelling of tritium washout by precipitation in the area of the nuclear power plant of Paks, Hungary

Tritium occurs in nature in trace amounts, but its concentration is changing due to natural and artificial sources. Studies focusing on natural tritium have to take into account the effect of artificial sources. Also, the impact of tritium is an important issue in environmental protection, e.g. in connection with the emissions from nuclear power plants. The present work focuses on the rain washout of tritium emitted from the Paks nuclear power plant in Hungary. Rainwater collectors were placed around the plant and after a period of precipitation, rainwater was collected and analysed for tritium content. Samples were analysed using low-level liquid scintillation counting, with some also subject to the more accurate ³He ingrowth method. The results clearly show the trace of the tritium plume emitted from the plant; however, values are only about one order of magnitude higher than environmental background levels. A washout model was devised to estimate the distribution of tritium around the plant. The model gives slightly higher concentrations than those measured in the field, but in general the agreement is satisfactory. The modelled values demonstrate that the effect of the plant on rainwater tritium levels is negligible over a distance of some kilometres.     

Assessing deposition levels of 55Fe, 60Co and 63Ni in the Ignalina NPP environment

Two RBMK-1500 reactor units operated in Lithuania in the 1987-2004 period (one of them was stopped for decommissioning in 2004). This study presents a preliminary investigation of surface deposition density levels of ⁵⁵Fe and ⁶³Ni in moss samples collected in the close vicinity of the Ignalina NPP. Non-destructive analysis by the HPGe gamma-spectrometry was followed by radiochemical separation. Radiochemical analysis was based on anion-exchange and extraction chromatography. ⁵⁵Fe and ⁶³Ni activities were measured by liquid scintillation counting (LSC). The results indicate that the deposition values of ⁵⁵Fe are generally higher than those of ⁶⁰Co and ⁶³Ni.