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针对热电离质谱仪由于强峰拖尾造成同位素比值测定结果不准确的问题,对谱峰产生拖尾的影响因素进行了分析,并提出了解决措施。结果表明:通过采取对离子源和法拉第接收杯进行清洗、以及对分析管道进行烘烤等措施可以减小谱峰拖尾,从而提高同位素丰度测量的准确性。 相似文献
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本文从铀资源勘查后遥感应用技术的研究内容出发,着重从物理意义相关性、反映地质规律深度相关性、时态相关性、平面赋存规律相关性,以及信息相关性的作用机理等5个方面对遥感信息与重力、航磁、航放等地球物理信息之间的相关性进行了初步探讨,为今后从定性和定量角度深入研究后遥感应用技术中遥感信息与其他地学信息之间的相关性开创了一个良好的开端。 相似文献
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为了筛选铀成矿有利地段,探索克山地区铀成矿前景,通过开展1:5万高精度航空放射性测量异常查证工作,并结合收集整理的相关地质资料,从航放异常特征、地质特征、能谱特征及土壤氡浓度特征等几个角度,对克山地区进行铀成矿条件分析。结果表明:该地区靠近小兴安岭地区,且盆地盖层具有较高的初始铀含量,铀源条件优良;地层宽缓,断裂发育,是深部烃类向上运移的通道,地表局部剥蚀强烈,形成构造天窗,成矿有利砂体大规模发育,并伴有后生改造作用和铀富集。克山地区航放异常集中分布,航磁推断构造发育,深部放射性信息突出,为砂岩型铀矿找矿提供了有益线索,为圈定找矿有利区段提供了依据。 相似文献
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正【英国《国际核工程》网站2019年4月25日报道】俄罗斯原子能工业公司(Rosenergoatom)2019年4月24日宣布,首座浮动式核电厂(FNPP)"罗蒙诺索夫院士"号的两座KLT-40S反应堆已完成综合测试。测试的目的是确认核电厂的技术参数符合设计,并确保其已做好投运准备。两座反应堆2019年3月31日投入满功率运行。俄原公司总裁安德烈·彼得罗夫说:"成功完成测试是俄原专家团队取得的一项伟大成 相似文献
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以光纤耦合全帧CCD方式制作的X射线探测器在实验室高精度X射线CT扫描中广泛应用。由于X射线的强穿透特性,全帧CCD探测器通常工作在无快门模式,图像拖影是该模式下必定存在的伪影。本文针对全帧CCD探测器CT扫描图像拖影校正进行研究,提出了非曝光行校正法校正投影图像拖影,避免了利用暗像元校正法校正投影图像拖影时可能会带来的条形伪影;针对动态曝光CT扫描,设计了基于辐射屏蔽的投影图像感兴趣区域快速读出模式,通过降低电荷转移时间有效抑制投影图像拖影的产生,提高探测器有效信号动态范围。实验结果表明:应用非曝光行校正法能有效校正投影图像拖影、提高投影图像质量;采用投影图像感兴趣区域快速读出模式可有效解决动态曝光CT扫描图像拖影校正难题。 相似文献
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现场X荧光分析技术是一种轻便、快速、高效、低投入的野外勘查技术.在航磁异常查证中应用现场X荧光分析技术,对新疆西天山某航磁异常点岩石与土壤中的Fe、Cu、Zn、Pb、As、Mn、Ni元素进行了分析,获得了该地区上述元素的分布,为航磁异常评价提供了依据.实践证明,现场X荧光技术为航磁异常查证提供了快速便捷的手段. 相似文献
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核动力装置是一多输入多输出、非线性、时变的复杂系统,其控制器通常采用基于模拟仪控的PID控制器来实现,系统参数易超调且响应时间较长。为改善核动力装置运行的动态品质和减小其系统的过渡时间,本文提出了在数字化仪控系统上实现专家系统和原控制器结合的协调控制器及其策略。为验证核动力装置协调控制技术及其策略,本文以1台全范围核动力装置模拟器为研究平台测试了协调控制技术。测试结果表明:基于数字化仪控技术来实现协调控制是可行的,协调控制器能有效改善核动力装置的动态运行特性,且协调控制器控制性能优于传统的PID控制器。 相似文献
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The Asociación Nuclear Ascó-Vandellòs (ANAV) is the consortium responsible for the Ascó and Vandellòs-II reactors. The reactors are Westinghouse-design 3-loop PWRs with an approximate electrical power of 1000 MW. In order to operate the reactors ANAV prepared an Integral Plant Model for each plant. The model is used for supporting plant operation and control from the point of view of safety and competitiveness. The Technical University of Catalonia (UPC) has been working with ANAV in order to establish, qualify and use these Best Estimate (BE) models. This paper develops a specific use of the Ascó plant model for operation support and tries to clarify a group of scenarios related to the total loss of feed water (FW) and the corresponding Feed & Bleed (F&B) recovery procedure. The study characterizes the procedure with different calculations and provides results that have become helpful in establishing the impact of partial availability of Power Operated Relief Valves (PORVs) and HPIS trains, the maximum time for starting the procedure and some considerations on heat sink recovery. The use of the BE model provides a consistent overview of the final problem. The results of the analysis are a first approach for operation support. 相似文献
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T. Czibk Z. Dezs Cs. Horvth S. Lipcsei J. Vgh I. Ps 《Nuclear Engineering and Design》2006,236(22):2356-2364
In 2004 the Hungarian Paks NPP completed a project for upgrading the reactivity measuring system applied during reactor startup experiments. Almost all components of the previous system were replaced, only ex-core ionisation chambers remained unaltered. New hardware and software components were introduced for neutron flux signal handling, for data acquisition, as well as for measurement evaluation and data presentation. High-precision picoamper meters were installed at each reactor unit, current signals are handled by a portable signal processing unit. The system applies an accurate on-line reactivity calculation algorithm based on the point-kinetic model with six delayed neutron groups. Detailed off-line evaluation and analysis of startup measurements can be performed on the portable unit, as well.The paper describes the architecture, data acquisition modules, services and man–machine interface of the new system. Functions and results are illustrated with measured data recorded during a startup of Unit 3. In 2003 and 2004 the RMR was installed and tested at all Paks NPP units successfully and now it is in regular use during unit startups.The second part of the paper illustrates an extension of the new system to perform reactivity measurements using the well-known Rossi-α and Feynman-α statistical methods. The modified system was needed to estimate the reactivity of a subcritical system formed by damaged fuel assemblies stored at the fuel service pit of Paks Unit 2. Theoretical background of the applied algorithms is outlined, then results of validation tests and on site measurements are treated. The measurements have shown that the subcriticality of the damaged fuel was sufficiently deep if the high boron concentration in the fuel service pit was maintained. 相似文献