Nominal Installed Capacity Utilization Factor (ICUF) as an Indicator of the Installed Capacity Utilization Efficiency of a Nuclear Power Plant

The nominal installed capacity utilization factor for power-generating units in different types of nuclear power plants is analyzed. It is shown that this indicator does not correlate with the operative regulation for servicing power-generating units, and it does not take into account the probability of unanticipated power decreases due to equipment failures and the present operating conditions of nuclear power plants in the common power system operating in Russia.     

核电机组设计可用率因子模型的研究

设计可用率因子是衡量核电机组设计和运行业绩一个非常重要的指标,也是世界核电运营者协会(WANO)对世界各核电厂经济性能进行对标的指标之一。提升核电机组可用率因子,是业内一直关注的重点和研究的方向。本文在中国改进型三环路压水堆(CPR1000)核电机组多年运行实践的基础上,搭建适用于群厂核电机组的可用率模型,提出提升设计可用率因子的方法和途径,为新建核电厂的设计提供思路和方法,也可供后续核电厂设计可用率因子指标的评价提供参考。     

核电厂运行的安全目标

描述了核电厂安全目标的定义、种类和形式，阐述了安全目标的分解以及安全目标的应用与评估，并以美国核管会（ＮＲＣ）的核电厂安全目标为例，讨论了在安全目标的发展和实际应用中可能存在的总理２及其解决途径。     

关于增加核电厂场外应急撤离时间管理要求的建议

在制定核电厂应急撤离计划和应急决策时,撤离时间估算是一项重要的技术支持手段。本文根据我国场外应急撤离的管理要求现状,借鉴美国撤离时间估算的相关经验,对核电厂场外应急撤离时间问题进行了分析,同时建议我国相关核安全管理规定中增加场外应急撤离时间的要求。     

核动力装置的可靠性与维修性问题

基于核动力装置的安全性要求,分析其可靠性与维修性特点。从设计、运行、管理、监督、应急等方面量化相关特性的评价指标,探讨核动力装置的安全性问题。     

核事故与国内现役核电机组核安全措施

根据核电厂核安全和辐射安全的设计防御准则,对核电史上三次重大事件进行分析,挖掘出核电事故主要因素：人因因素和超过设计值的自然灾害。同时结合国内核电厂的设计参数和运行参数,对发生类似事故进行研究比较,提出必要的预防方案。国内现役核电厂在运行安全技术上,已经可以充分预防人因事故的发生,对于超过设计值的自然灾害及外在因素引起的事故,还应重新考虑安全标准。核电厂在建设和运行过程中,需要充分考虑在极端环境下,如何将核辐射和泄漏的危害程度降低至政府以及公众能够接受的水平。     

Utilization Factor of Nuclear Material in LMFBR

The effects of γ-irradiation on a simulated nuclear waste glass were studied by electron spin resonance spectroscopy (ESR), and were compared with the results on silica glass and Pyrex glass. Three kinds of glasses were γ-irradiated up to the dose of 1.22 MGy and the ESR spectra were obtained. The intensity of ESR spectra were obtained as a function of irradiation dose and annealing temperature.

The spectrum of the waste glass was characteristic of two typical peaks, Peak 1 was the strong resonance at g=4.3 showing the existence of four coordinated Fe³⁺ and Peak 2 was the weak and broad resonance at g= 2.0 showing the existence of six coordinated Fe³⁺. The ESR spectra of the waste glass before and after γ-irradiation were almost overlapped and a little difference only in the intensity was observed. While in silaca glass and Pyrex glass, the peaks from E'γ center and boron-oxygen hole center (BOHC) were observed to arise after irradiation. The absolute intensity of. Peaks 1 and 2 described above changed in complicated way depending on the dose. The result suggests oxidation or reduction of iron takes place in the waste glass depending on the dose. The isochronal annealing of irradiated glasses shows most of γ-ray- induced damages in the waste glass are restored even at room temperature, although most of the damages in silica glass and Pyrex glass are disappeared at the temperature from 550 to 600 K. The results show that the waste glass with a few weight percent of iron is resistent to radiation than other commercial glasses.     

Sorption and Desorption of Radionuclides on the Structural Materials of a Nuclear Power System as Applied to Nuclear Power Plants with RBMK Reactors during Shutdown

The sorption and desorption of radionuclides on structural materials are studied as a function of the content of corrosion-activating ions, oxygen, hydrogen peroxide, and corrosion inhibitors in water. The strongest desorption is observed in aerated water containing chloride ions and the weakest desorption in a deaerated medium. The amount of desorbed radionuclides is correlated with the rate of corrosion of metals – it is highest on perlite steel (No. 20 steel) and lowest on zirconium alloys. Anode inhibitors prevent the corrosion of steel and transfer of radionuclides into the coolant.The sorption of radionuclides depends on the sample material. The highest sorption is observed on perlite steel and the lowest on zirconium alloy. Adding an inhibitor to the contaminating solution counteracts the effect of sorption, depending on the type of the structural material and radionuclide, and decreases it manyfold.     

Development of a Method of Selecting Important Alarms for Nuclear Power Plants

Presenting important alarms selected from a large number of activated alarms provides useful operational support under a transient status in a nuclear power plant. We have developed an alarm processing method which selects and presents important alarms depending on plant status.

In this method, important alarms are selected, first, based on physical relationships between alarms and component status including alarms themselves and second, even more important alarms are selected from the previously selected alarms according to the identified initial event causing the transient. Identification of the initial event is implemented by a neural network. The identified initial event and selected important alarms are presented to show the cause and influence of the transient.

A prototype based on the above alarm processing method was validated during the start-up test at Kashiwazaki Kariwa Nuclear Power Plant Unit Number 4 of Tokyo Electric Power Co. The initial events, which were load rejection, turbine trip and main steam isolation valve closure, were correctly identified and about 30% of all activated alarms were selected as important. It was verified by an operating expert that the presentation of the identified initial event and the selected important alarms were effective to understand rapidly and correctly the transient status of the plant.     

核电厂计算机化规程系统开发

利用C语言在实时嵌入式操作系统 VxWorks上开发了一种用于正常操作的计算机化规程系统(CPS).本文介绍了系统的组成,并对人-机界面的设计进行了分析.以冷启动为例,验证了CPS的技术可行性.结果表明,CPS能够提高操作的准确性,减轻运行人员的工作负担.     

Automated Control and Safety of Nuclear Power Plants

The conceptual problems of developing and modernizing an automated system for the control of a technological process for nuclear power plants, which are under construction, or are currently operating, are discussed. Attention is focused on the human factor in the control of a nuclear power plant. The prospects for solving problems such as the optimal – from the safety standpoint – separation of control functions between man and machine, choice of means of automation adequate for the importance of the functions being performed with respect to safety, determination of the concept of the operator's job, and the systems for supporting the operator's work, and development of a modern man–machine interface, are examined.The solution of these problems is studied on the basis of a homocentric model of an automated system for controlling a technological process. The model uses extensively subsystems for supporting the work performed by the operator. It is noted that a supervisor role for the operator is preferable, since it provides the best psychological work environment. 11 references.     

核电厂1E级电缆的核安全审查

阐明对核电厂1E级电缆核安全审查的基本要求.     

核动力厂抗震设计要求的变化

比较了国际原子能机构(IAEA)新版的安全导则"Seismic Design and Qualification for Nuclear Power Plants"(NS-G-1.6)与老版的50-SG-D15以及我国的核安全导则"核电厂的抗震设计与鉴定"(HAD102/02)之间的变化,分析了其变化的背景.就其在我国的可实施性,提出了看法和建议.     

基于MSET和SPRT的核动力装置异常状态监测技术研究

对核电厂反应堆冷却剂系统在线监测与预警技术进行研究。在分析反应堆冷却剂系统组成特点及故障特点的基础上,采用多变量状态估计(MSET)和序贯概率比(SPRT)技术,对系统的变量进行估计预测和异常判断。一旦发现异常,即可触发故障诊断单元或给出预警。验证表明,通过MSET和SPRT技术结合的方法,可以较好地完成对变工况下的反应堆冷却剂系统异常监测任务。     

核电厂应急撤离的有关问题

概述了国内外有关核电厂应急撤离的法规、导则,介绍了影响应急撤离的众多因素,对应急撤离路线设置进行了讨论。     

核电站风险监测器软件开发研究

在大型概率安全分析软件系统Risk A的基础上,开发了具有自主知识产权的核电站风险监测器Risk Amgel.使用Risk watcher及大亚湾核电站的部分参考模型对Risk Angcl系统进行了测试.测试结果表明,Risk Angel完全可以用于核电站实时风险的计算.     

地下核电厂经济性分析

经济性是否合理是地下核电厂是否值得建设的重要因素。通常认为增加地下工程的费用导致地下核电厂的经济性比地面核电厂差;然而,地下核电厂的概念设计结果表明:与同等规模同等堆型的地面核电厂相比,地下核电厂的静态投资增加幅度小于12%,在可接受的范围内。考虑到地下核电厂采用封固埋葬的退役方式成本仅为立即拆除的30%、核安保所需的人数和经费小于地面核电厂,具备取消应急计划区的可能性,地下核电厂的综合经济性优于地面核电厂。     

压水堆核电厂氚排放源项的计算及验证

氚是核电厂放射性流出物中重要的核素,氚源项也是核电厂辐射环境影响评价中最重要的关注点之一。本文基于压水堆核电厂中氚的产生机理建立氚源项的计算模型,并结合我国某在役核电机组2003—2018年运行经验反馈数据,对理论计算模型的结果进行对比分析。研究结果表明,本文建立的氚的计算方法所得到的模拟值与实际运行情况相符,本文氚排放计算采用的计算模型和假设是合理的。