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基于FPGA的核电厂安全级仪控系统验证与确认 总被引:1,自引:0,他引:1
现场可编程门阵列(FPGA)设备因具有行为确定、结构简单、时间响应快、易于取得监管和取证等优点,越来越广泛应用于核安全系统,特别是新一代核电厂安全级仪控系统。FPGA安全级仪控产品可以克服核电仪控系统设备老化问题,是目前核电厂仪控系统进行技术改造的首选方案,满足三代核电高安全性与高可靠性的要求。同时,随着我国核电建设事业的快速发展及三代AP1000技术的引进,被誉为核电厂"神经系统"的数字化控制系统(DCS)的自主化越来越受到人们的关注。但是,核电业主和国家核安全管理当局都要求对FPGA安全级DCS系统进行严格的验证与确认(VV),以保证FPGA安全级DCS产品的高质量和高可靠性。论文探讨了基于FPGA技术的安全级DCS系统研发过程VV生命周期模型、VV标准体系、VV活动和方法,讨论了FPGA技术安全级DCS产品VV可能采用的仿真和测试技术,并提出了FPGA开发工具鉴定的方法。 相似文献
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介绍了秦山核电厂扩建项目(方家山核电工程)仪控系统的多样性设计方案,从设计的依据、分析方法、分析结果等方面进行论证,证明仪控系统多样性设计的必要性及正确性。 相似文献
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自诊断功能是核安全级数字化仪控系统的关键功能,对核安全级数字化仪控系统本身的RAMS特性,以及核电厂整体安全性和可用性有直接影响。本文基于RAMS分析评估技术,形成了以潜在故障模式为主的自诊断功能设计基准,在此基础上提出了一整套包括故障诊断、故障处理、诊断信息上报和报警指示功能的核安全级数字化仪控系统自诊断功能设计方案,并在和睦系统上进行了设计实现。实测结果表明,和睦系统可以实时在线监视自身运行状态,能够及时处理、上报和精确指示所有设计基准范围内的异常,大幅增强了故障定位能力,提高了和睦系统的可维修性,充分满足核电厂整体安全性和可用性要求。 相似文献
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大亚湾核电站电气、仪控设备及备件一直从国外进口,目前开始受到国外各种因素的影响,出现备件供应无法保障的问题,因此,大亚湾核电站在仪控设备的国产化方面进行了尝试。经过调研,认为我国已经具备了自主生产或研究开发核电仪控系统的能力,可以从模拟仪控系统的板卡及配件替代品入手,逐步发展到整机柜的替代,最终实现先进的数字化主控系统的自主研究开发和生产。解决电气、仪控设备国产化首先需要解决核级电气、仪控系统设备的设计、制造、试验、可靠性评估方面的一系列问题,本文介绍了电气仪控系统备件国产化过程中的研究开发技术路线、所遵循的原则、技术标准、以及项目管理经验。 相似文献
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根据中国和加拿大核安全法规的要求,对初步安全分析报告和最终安全分析报告中的第15章进行了核安全评审。本文介绍了事故分类、大破口失水事故(LBLOCA)和蒸汽发生器传热管断裂(SGTR)事故分析的核安全审评概况。 相似文献
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Jrg Fischer 《Nuclear Engineering and Design》1991,125(3)
The IAEA Symposium on Fire Protection and Fire Fighting in Nuclear Installations covered a large scope in the field in order to provide the opportunity for screening all aspects of present technology, research and development, standardization, licensing and fire fighting practices. Although application to any nuclear facility was within its scope, the majority of presentations concerned nuclear power plants. The approach to fire protection is the classical one in all plant designs: reduction of fire loads, appropriate zoning, manual and automatic extinguishment. However, methods of analysis and consequence prediction are changing. Computerized fire modelling is becoming a powerful tool in this area; probabilistic analytical methods are being improved, though they are not yet used widely for fire hazards. Differences in opinion were revealed in the definition of barrier resistance, the prediction of cable insulation behaviour and the optimal design of extinguishing systems. Greater international co-operation, especially in these areas, may be a good way of optimizing results with limited resources. Discussion contributions showed interest in exchange of experience in more specialized topics and encouraged the IAEA to increase its activity in the area of fire protection. 相似文献
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J.C. de la Rosa A. Escrivá L.E. Herranz T. Cicero J.L. Muñoz-Cobo 《Progress in Nuclear Energy》2009,51(1):32-66
In the last two decades condensation on the containment structures in presence of noncondensables has received substantial attention by nuclear scientists and engineers. The reason is that many Generation III and III+ reactors rely on passive systems operating under natural circulation. As a consequence, a vast number of publications have been made in the open literature. This paper reviews the specific physical phenomena that are involved in condensation and discusses how they have been considered in the different available models. In addition, it explores the data that have been used for validation and provides some insights on the effective suitability for this purpose. Finally, the paper summarizes the current codes' capabilities to deal with wall condensation in the presence of noncondensables according to the most recent available validation exercises. 相似文献
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为确定高通量工程试验堆(HFETR)保持许可证审批依据仍有效的程度及满足现行安全标准和实践的程度,从2009年至2011年参照现行核安全法规和导则对HFETR进行了第2次定期安全审查(PSR)审评。审评的重点为实际状态、安全分析、安全性能、老化管理及其他要素等5方面。审评中考虑了5.12汶川大地震发生后对HFETR进行的震后综合检查与评估结论。HFETR目前实际状态和安全状况的检查、分析及校核结果表明,通过多年来进行的一系列整治、改造、试验和维护,HFETR的停堆、冷却及包容等三大安全功能基本得到保持。 相似文献
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Samuel D. Harkness Charles C. Baker Mohamed A. Abdou John W. Davis William Hogan Gerald L. Kulcinski Michael Mauel Carl McHargue Robert Odette David A. Petti Paul Shewmon Stewart J. Zweben 《Journal of Fusion Energy》2000,19(1):45-64
This report presents the results and recommendations of the deliberations of the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee Panel on the Review of the Fusion Materials Research Program carried out during 1998. Metrics evaluated included evidence of recognition, publications per worker, new people attracted to the work and significance of recent accomplishments. 相似文献
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高温气冷堆是我国重大专项的先进核电厂项目,高温气冷堆PSA报告是其执照申请文件的重要组成部分。简要介绍了高温气冷堆PSA报告的审评情况,并对高温气冷堆PSA审评过程中的有关问题进行了初步的探讨。 相似文献
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手持式γ谱仪用核辐射探测器综述 总被引:1,自引:0,他引:1
介绍了γ谱仪探测器基本性能评价指标,分析了手持式γ能谱测量中常用的核辐射探测器,如高纯锗、碘化钠、碘化铯、碲锌镉和溴化镧等的主要性能特点,指出碲锌镉和溴化镧的产生与发展,以及高纯锗谱仪小型化是近年来手持式γ谱仪探测器技术的主要进展。为了应对不断增长的手持式放射性核素识别应用需求,建议加强碲锌镉和溴化镧探测器研制及其在手持式谱仪中的应用研究。 相似文献