共查询到18条相似文献,搜索用时 218 毫秒
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核电厂应急柴油发电机组随着容量的不断增大,已越来越难以满足应急工况下10 s内快速启动的要求.超级电容作为一项新兴的储能技术,具有传统储能技术不可比拟的短时间内快速放电能力.本文提出了将超级电容作为核电厂应急柴油发电机组启动期间后备中压电源的设计方案,以延缓应急工况下对于应急柴油发电机组快速启动的时间要求,有效提高应急... 相似文献
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AP1000核电站在提高安全系数的基础上,充分利用大量的非能动技术,取消了应急柴油发电机等核级能动设备,减少了操作员的干预动作,降低了人因因素的影响。使用尽可能少的系统和设备,使得布置简化;采用了维修周期更长甚至免检修的先进设备,减少系统及设备之间的接口,提高了核电厂自身应对各种严重事故或自然灾害的安全响应能力。其中主泵系统由于它的重要性和特殊性,也是技术引进的重点项目;文章通过对主泵的作用和电气系统原理分析,阐述了电气设备的配置及特殊结构。 相似文献
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应急柴油发电机(EDG)作为核电厂重要安全设备,主要用于应对丧失厂外电事故。为确保EDG的可靠性,应制定维修计划并定期进行各种预防性维修。鉴于EDG维修时间较长,应考虑由于维修造成的不可用给“华龙一号”核电厂带来额外的安全风险,这成为“华龙一号”核电厂EDG数量配置的重要考虑因素之一。根据最新的核安全要求,将导出乏燃料贮存设施所贮存燃料的热量上升为基本安全功能,相比于国内的二代堆型,“华龙一号”考虑了乏池冷却相关设计基准工况,这直接导致2×100%EDG配置方案难以找到合适的EDG维修窗口。本论文的主要目的就是利用确定论和概率论安全分析方法对EDG的维修窗口进行详细分析,另辟蹊径为EDG提供允许维修时间。分析结果表明,2×100%配置下EDG允许维修时间能够满足维修实际需要。因此,HPR1000采用2台应急柴油发电机的配置方案下能够开展维修。 相似文献
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将系统可靠性分析方法GO法与Markov法相结合,对核电厂概率安全分析(PSA)中厂外电源丧失(LOOP)后柴油发电机应急响应系统在24h内缓解全厂断电(SBO)事件中的动态过程进行分析,解决了维修相关存在下可修系统可靠性精确计算问题,并通过创建GO法“备用门”操作符真实地模拟应急响应系统工作的逻辑关系.通过将2种可靠性分析方法相结合使用的尝试,使之与柴油发电机应急响应系统存在维修相关的实际情况相适应,拓展了2种方法的分析领域,同时能够更为精确地得出SBO对系统安全运行的影响. 相似文献
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柴油发电机电源系统故障树建模是整个核电厂电力系统概率安全分析体系中最为重要的内容之一.在柴油发电机电源系统的故障树建模过程中,会出现交流电系统、直流电系统的逻辑循环,如不做处理,将无法得到故障树顶事件的失效概率.本文在国内首次通过建立完整的柴油发电机电源系统故障树模型,解决柴油发电机电源系统故障树建模中的逻辑循环截断问... 相似文献
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目前福清一期核电厂应急柴油发电机组(EDG)采用法国标准RCC-E 2005进行定期试验,在低功率定期试验时对柴油发电机的保护不充分,存在严重损坏设备的风险。为解决该问题,本文详细分析IEEE 387标准对应急柴油发电机组定期试验的规定,依据IEEE 387标准对应急柴油发电机组的定期试验进行改进,取消原来的低功率试验,采用在机组正常运行期间进行并网带载的试验方法,并详细分析改进后的试验内容,使EDG定期试验的方法更加经济和安全,目前改进内容已得到了核安全监管机构的认可,为核电厂的相关定期试验改进提供了重要参考。 相似文献
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Man Cheol Kim 《Journal of Nuclear Science and Technology》2017,54(10):1029-1035
The Fukushima accident raised concerns about the preparation level of nuclear power plants against multi-unit accidents. Under dual-unit station blackout (SBO), it is generally considered that the alternate AC diesel generator (AAC DG) is connected to only one unit, and core damage is inevitable in the other unit. Based on the lessons from Fukushima Daiichi Units 5 and 6, which successfully mitigated the situation by sharing one emergency diesel generator, this study investigates the feasibility of shared use of the AAC DG under a dual-unit SBO. A thermal-hydraulic (TH) code analysis with conservative assumptions demonstrated that both units are able to withstand and recover from dual-unit SBO by the shared use of the AAC DG. The review of the TH code analysis results by changing the conservative assumptions to more realistic assumptions also provide strong support for the same conclusion. After being properly incorporated into operational procedures, such as emergency operating procedures, the shared use of the AAC DG under a dual-unit SBO is expected to significantly reduce plant risk. 相似文献
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V. M. Tarasenko 《Atomic Energy》2003,94(2):76-81
The purpose of this paper is to show that during the operation of safety systems at nuclear power plants the principle of independence from the power system, which is one of the basic principles inocrporated in the design of safety systems, is not satisfied and the power system, especially if it is deficient, cannot guarantee the required electricity and protection for safety systems from general failures. To satisfy the independence principle, guarantee the required quality of electricity, and protect the safety systems in nuclear power plants from general failures, it is proposed that the presently operative algorithm for starting up diesel generators be reexamined. When the safety systems at nuclear power plants perform their required functions, they should operate from autonomous diesel generators at the nuclear power plant, which are equipped with electricity quality regulators (frequency and voltage), and not from the power system. It is also suggested that the variant of the algorithm where diesel generators are started up as a preventative measure when the quality of the electricity in the power system drops below admissable limits be reexamined. 相似文献
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Shih-Jen Wang Chun-Sheng Chien Show-Chyuan Chiang 《Nuclear Engineering and Design》2006,236(12):1330-1333
Reactor coolant system (RCS) injection using accumulator is an important strategy for both emergency operating procedure (EOP) and severe accident management guideline (SAMG) of pressurized water reactor (PWR) nuclear power plant. Once accumulator injection starts, the operator is requested to close the accumulator isolation valve to avoid nitrogen gas flow into RCS as the water level is low. Current accumulator water level indication system is not designed for this purpose. In emergency operating procedure, it relies on the steam generator pressure to close the accumulator isolation valve.The purpose of this paper is to develop a computational aid for estimating RCS injection volume of accumulator. First of all, simple accumulator model is verified using the plant data during a station blackout incident of Maanshan nuclear power plant. An isentropic expansion model is found better than adiabatic expansion model. Then, a computational aid is developed based on this model. Using this computational aid, the accumulator water level can be judged directly from the accumulator pressure. This computational aid can be applied for typical PWR nuclear power plants in both emergency operating procedure and severe accident management guideline. 相似文献
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为保证我国正在新建的某研究堆安全运行,通过介绍该研究堆应急电力系统的设计准则、系统结构、功能、设备组成等,分析系统的柴油发电机组、不间断电源(UPS)以及安全级蓄电池组的容量确定过程中应考虑的关键要素,并设计了一套应急电力系统作为反应堆的专设安全设施,对其容量进行了计算。结果表明:该系统的柴油发电机组容量1000 kV?A、不间断电源最大容量600 kV?A、安全级蓄电池组最大容量5000 Ah,在2路外电源丧失后能不间断地向反应堆安全系统供电72 h。因此,该应急电力系统能够保证反应堆安全运行。 相似文献
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