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1监测目的和内容 2008年度,根据中国原子能科学研究院常规监测计划要求,辐射安全研究部辐射监测与评价研究室现场辐射监测组对我院的辐射工作场所(监督区)进行了监督性监测。 相似文献
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王绍林 《中国原子能科学研究院年报》2007,(1)
1监测目的和内容
2007年度,根据中国原子能科学研究院常规监测计划要求,辐射安全研究部辐射监测与评价研究室现场辐射监测组对我院的辐射工作场所(监督区)进行了监督性监测。 相似文献
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设计实现了核事故应急辐射环境实时移动监测系统,包括三个子系统:车载辐射环境现场数据监测系统、无线数据传输系统和监测中心数据处理系统.通过现场多次测试证明,系统满足核应急监测实时数据采集和传输的要求. 相似文献
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在田湾核电站自动辐射监测系统设计中,将辐射监测系统的功能分为工艺监测、场所监测、沾污监测和个人剂量监测,功能分类明确清晰。扫描式液体、气体γ谱仪首次应用于核电厂现场,减少了人员现场取样,并能快速实时获取数据。超设计基准事故的高量程γ测量仪的设置,为福岛核事故后的核电厂设计提供了参考。采用数字化技术,辐射监测信息及相关的工艺信息,可以集中显示在一个工作站和同时分类显示在不同的工作站;另外各工作站也具有控制功能,能实现远程操作辐射监测仪表,完成辐射监测信息的分散控制和集中管理。 相似文献
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1监测目的和内容
2006年度,根据中国原子能科学研究院常规监测计划要求,辐射安全研究部辐射监测与评价研究室现场辐射监测组对我院科研、生产、运行及技术服务过程中产生辐射的工作场所进行了监督性监测。 相似文献
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RS485Modbus是核电厂辐射监测系统设备常用的通讯方式。论文根据核设施辐射监测系统设计和工程实践经验,介绍了该通讯方式的测试调试方法,并针对通讯问题提出解决方法和改进建议,可供各类辐射监测系统设备在软件开发、测试和现场调试时参考。 相似文献
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在核设施发生重大核事故后,快速进入事故区域获取核泄漏及放射性污染现场的辐射分布情况具有重要意义。当重大核事故发生后,通常伴随道路的严重损毁,致使核辐射探测器无法随人员和车辆通过地面通道进入核事故现场进行辐射监测。为了克服传统的核应急监测方式易对人员辐射伤害、机动性差及效率低等问题,本研究设计并实现一种无人机载辐射监测系统,能够迅速进入放射性污染区域上空进行辐射监测。无人机辐射监测系统主要包括宽量程G-M计数管、溴化铈闪烁体探测器、数据采集系统与数据传输系统,将以上装置搭建在无人机上可执行0~100 m的低空实时辐射剂量率和能谱测量任务。 相似文献
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基于3G技术的远程辐射应急监测系统研究 总被引:1,自引:0,他引:1
邢丽丽 《核电子学与探测技术》2010,30(3)
根据辐射事故应急监测的需要,设计了一套辐射应急监测系统,包括无线通信网络、辐射应急监测车和指挥控制中心。采用GPS/GIS技术实现对事故现场的定位及事态估计、同时利用目前最先进的3G无线通信网络实现了现场数据的实时传输,指挥控制中心的远程指挥和决策支持等功能,能够很大程度上提高辐射事故的应急处置效率。 相似文献
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介绍了一种基于全集成自动化(Totally Integrated Automation,简称TIA)的区域Υ辐射监测网络系统,过程控制简单而安全,方便信息网络和现场总线及仪表的集成,设计模块化,系统扩展性强,实现了管控一体化,对辐射监测系统国产化具有积极作用. 相似文献
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本文介绍一种快速监测钍废水中放射性核素浓度的方法。该法简单,其具体步骤是将一定大小的织纤布浸泡于废水中,搅动一定时间后取出,冲洗并烘干,即可直接测量。在一小时或更短的时间内便可得到结果。实验发现4号布对钍系有选择性吸附的能力。当废水中所含放射性核素以钍系为主时,所得实验结果与放化分析结果相差大约为10%,对含有少量铀的钍废水监测下限为10~(-11)居里/升。 相似文献
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脉冲堆燃料的安全特性及其在小型动力堆中的应用 总被引:1,自引:5,他引:1
本文介绍了脉冲堆U-ZrH_(1.6)燃料的安全特性及具在国外小型动力堆中的有关应用情况。最终指出,U-ZrH_(1.6)是一种完美的燃料概念,除脉冲堆外,在小型动力堆中有着广阔的应用前景。 相似文献
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《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》1988,35(1):43-49
Until now, the most sensitive glass for recording and identifying nuclear particle tracks has been VG-13, a phosphate glass that is not produced in the USA because it contains uranium. In a search for a replacement for VG-13, we have studied about 150 phosphate glasses, as well as a few other types. We summarize here the results of that study. We have developed a new glass, BP-1, composed of 65 wt.% P2O5, 25 wt.% BaO, 5 wt.% Na2O, and 5 wt.% SiO2, which has several advantages over VG-13: it contains no uranium, it is colorless and transparent, and it is more sensitive to ionizing particles. 相似文献
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介绍由主控计算机和多个探测通道组成的辐射监测系统,可以对多种辐射的能量、强度、剂量率、剂量及剂量当量进行监测.该系统虽然是为4MV静电正离子加速器辐射监测设计制作的,但同样适用于类似条件的其他场所的辐射监测. 相似文献
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流量测量用非均匀分布多孔式整流器的研究 总被引:4,自引:0,他引:4
标准节流装置广泛应用于过程流量测量.但它要求上、下游必须有足够长的直管段,否则,将会增加测量的误差.安装整流器是解决直管段长度不够的有效途径.本文作者研究的非均匀分布多孔式整流器具有整流效果好、结构简单、安装方便及造价低廉等优点,可在许多场合推广使用。 相似文献
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This paper presents the investigation of Passive Autocatalytic Recombiners' (PARs) capabilities for hydrogen recombination in case of Station blackout scenario. The assessment was performed for both types of WWER fuel assemblies – the old Modernistic type of fuel assemblies (TVSM) and recently installed new Alternative type of fuel assemblies (TVSA) in Kozloduy NPP. The main difference between both types of fuel assemblies is the different geometries, masses of internals materials as well as different burnable poisons. To investigate the PARs' capabilities it has been performed comparison of fuel behaviour of both types of fuel assemblies.To perform this analysis it has been used MELCOR “input model” for Kozloduy Nuclear Power Plant (KNPP) WWER-1000. The model was developed at the Institute for Nuclear Research and Nuclear Energy (INRNE) for investigation of severe accident scenarios. The model provides a significant analytical capability for the Bulgarian technical specialists, working in the field of the NPP safety, for analysis of core and containment damaged states and the estimation of radionuclides' release outside fuel cladding.To assess the PARs' capabilities it was used the acceptance criterion for containment integrity to be 8% hydrogen concentration. This criterion was based on the decision of RSK (Germany commission for reactor safety).Generally, based on the performed analyses it was made a conclusion that using both types of fuel assemblies it was not disturbance of PARs' capabilities and safety criterion of NPP. 相似文献
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Nafiseh Zare Author Vitae Author Vitae Mohammad Rahgoshay Author Vitae Author Vitae Shabnam Kia Author Vitae 《Nuclear Engineering and Design》2010,240(11):3727-3739
In this study, a new and innovative method is introduced for analyzing neutronic and thermal-hydraulic calculation. For this aim, VVR-S research reactor was selected, and the calculation procedure was performed for it. WIMS, CITATION and COBRA-EN codes were used for investigation. Calculation model consists of two sub-models: neutronic and thermo-hydraulic. The neutronic model uses WIMS and CITATION codes for neutronic simulation of the reactor core and calculating flux and power distribution over it. WIMS code simulates the fuel assemblies and CITATION models the core. The thermal-hydraulic model uses COBRA-EN code for performing the relative calculation. In this study, FORTRAN 90 program is used for linking two sub-models and performing the calculation. The proposed procedure is performed for VVR-S analysis and finally, the obtained results are compared with the experimental results that show good agreement with it. 相似文献