核设施退役虚拟仿真系统框架研究

退役核设施具有放射性,其退役过程危险且复杂,基于虚拟现实等技术的退役虚拟仿真系统可为退役工程提供辅助工具。本文在分析国内外研究成果的基础上,结合一专项退役工程的需求提出了该虚拟仿真系统的功能模块组成。基于软件开发技术进一步给出了系统的框架结构,并对各模块实现的相应技术进行了分析和探讨。分析中结合了计算机软硬件技术的最新研究成果,对退役中的切割、爆破、流体及放射性等的仿真技术进行了探讨。分析表明,基于普通个人计算机也可实现退役过程的全面虚拟仿真。经专家论证本方案具有可行性。     

氚靶制备玻璃系统的退役

介绍了某氚靶制备玻璃系统的退役流程及退役过程中氚的辐射防护,估算了退役过程中氚对公众和工作人员的照射剂量,两者的照射剂量均远低于国家标准。     

Development of Acoustic Leak Detection and Localization Methods for Inlet Piping of Fugen Nuclear Power Plant

The development work carried out on Fugen NPP is focused on detection of a small leakage on the reactor's inlet feeder pipes at an early stage by an acoustic leak detection method with usage of high-temperature resistant microphones. Specifically, the leak rate of 0.046 m³/h has been chosen as a target detection capability for this system. A cross-correlation technique has been studied for leak detection under low signal-noise ratios. The study shows that the sound diffusion on piping causes distortion of leak signals that results in their low correlation. A leak-location estimator and multi-channel correlation value, associated with estimated leak position, have been employed to detect such low-correlated leak signals. A method based on cross-correlation of signal spectral components has been proposed to deal with non-stationary leak signals. Joint-Time-Frequency-Analysis has been applied to analyze such signals, whilst a Wavelet decomposition technique has been used to extract their short-term spectral fluctuations. Since the spectral components are less affected by signal distortion, they provide higher correlation value and can be applied for leak detection under lower signal-noise ratios. The possibility of detecting and locating a small leakage by the methods proposed has been demonstrated by a number of simulation tests conducted on the Fugen NPP site.     

核设施退役中若干环境相关问题的探讨

核设施退役有利于消除核安全隐患,减少辐射环境风险,是环境保护的一项重要活动。本文讨论了在核设施退役过程中应重点关注的几个问题:退役目标和剂量约束值、退役过程中有关控制值的制定、放射性废物管理以及退役过程中和退役终态的监测。并结合退役项目说明了在退役实施中应该重点关注的环境相关问题。     

Radiation imaging using a compact Compton camera mounted on a crawler robot inside reactor buildings of Fukushima Daiichi Nuclear Power Station

ABSTRACT

The Fukushima Daiichi Nuclear Power Station (FDNPS), operated by Tokyo Electric Power Company Holdings, Inc., went into meltdown in the aftermath of a large tsunami caused by the Great East Japan Earthquake of 11 March 2011. Measurement of radiation distribution inside the FDNPS buildings is indispensable to execute decommissioning tasks in the reactor buildings. We conducted a radiation imaging experiment inside the reactor building of Unit 1 of FDNPS by using a compact Compton camera mounted on a crawler robot and remotely visualized gamma-rays streaming from deep inside the reactor building. Moreover, we drew a radiation image obtained using the Compton camera onto the three-dimensional (3-D) structural model of the experimental environment created using photogrammetry. In addition, the 3-D model of the real working environment, including the radiation image, was imported into the virtual space of the virtual reality system. These visualization techniques help workers recognize radioactive contamination easily and decrease their own exposure to radiation because the contamination cannot be observed with the naked eye.     

Developing Integrated Decommissioning Information Management System (IDIMS) of Nuclear Facilities

In Taiwan, the Taiwan Research Reactor (TRR) was shut down in January 1988, and a few nuclear facilities were accompanied to stop operation within Institute of Nuclear Energy Research (INER). For public health and safety reasons, INER dismantled step by step its expired nuclear facilities. Integrated Decommissioning Information Management System (IDIMS) was developed to ensure safety of dismantling and to record all activity data during the decommissioning project. These recorded activity data range from data of planning, licensing, post-operation to those of radioactive waste management and storage. In addition, IDIMS was expected to preserve decommissioning knowledge using information technology from practical data and problem solving. It also is anticipated that IDIMS will be an important knowledge repository and design base for decommissioning projects of nuclear power plants in Taiwan.     

核电站工程管理计算机系统的开发与应用

根据广东大亚湾核电站和岭澳核电站在工程建设中的经验,阐述了核电站建设中采用计算机管理的必要性以及实施办法。     

核电工程数据库的开发与ORACLE系统的选择

根据核电工程数据库的开发需求及ＯＲＡＣＬＥ数据库管理系统的特性，提出了选购ＯＲＡＣＬＥ系统的一些看法。     

专业化核电工程公司的组建

中国核电快速发展,核电工程项目管理必须实现专业化.应市场要求,组建核电工程公司,为业主提供核电工程项目管理和总承包服务.组建核电工程公司,必须明确公司组建目的和企业核心竞争力,机构设置应着眼于企业经营管理和发展,强化项目管理和控制,提高风险抵御能力.     

核电工程数据库工作的几点思考

针对核电工程数据库工作，根据几年来的工作体会，在建立核电数据资源法制管理渠道，规划实施中的问题，提高管理人员素质等方面，发表了看法和意见。     

Development of Telerobotic Systems for Reactor Decommissioning, (III)

This paper describes the telerobotic system for reactor decommissioning in the scope of engineering demonstration of dismantling radioactive reactor internals of an experimental boiling water power reactor JPDR. The total system consists of a telerobotic manipulator system equipped with a multi-functional amphibious slave manipulator with a load capacity of 25 daN, a chain-driven transport system, and a computer-assisted monitoring and control system. Preceding to the application of the telerobotic system to actual dismantling operation, a mockup test was performed of dismantling the simulated reactor internals of actual-size by the method of underwater plasma arc cutting in order to study the performance of the telerobotic system in a realistic environment. The system was then successfully applied to dismantling the actual reactor internals according to the JPDR decommissioning program.     

核电厂集成式污染监测和剂量管理系统开发与应用

随着电子剂量计、控制区出入口污染监测设备、热释光测读装置和全身计数器等设备的数据接口逐渐开放,核电站可以将上述设备的数据联通,形成一套完整系统。核电厂可以根据辐射防护管理的需要对数据进行集中管理、长期储存和深化应用,将原本由人工完成的管理工作通过信息化和智能化的手段高效完成。本文介绍某核电厂集成式污染监测和剂量管理系统的系统组成和基本功能、系统内外部数据接口设计,分析系统应用效果,提出在个人剂量调查与干预、最优化情况执行反馈、集体剂量与报警信息的管理与趋势分析等几个方面的深化应用。     

田湾核电站信息化建设中的数据管理

文章通过对田湾核电站数据管理职能的识别与阐述,介绍了田湾核电站数据管理体系建设、数据管理体系成熟度模型构建、数据管理体系成熟度自我评估以及数据质量改善等领域工作,并结合大数据时代特征,阐述了数据的科学管理对企业生产运营的影响,进而对数据管理的远景进行了展望.     

RCM在保证田湾核电站ARMS可靠性方面的应用

将以可靠性为中心的维修(RCM)理论与在自动辐射监测系统(ARMS)调试、运行、维护过程中的工作实践相结合,分析总结通过模件的可靠性设计、系统的冗余性设计以及采取状态监测、周期性维护、定期试验、纠正性维修和技术改造等一整套维护策略来保证ARMS运行的可靠性,并从信息收集、设备分级和人员准备等方面对今后RCM在ARMS维修过程中的应用提出建议。     

核电厂安全控制系统TXS虚拟机软件的设计与开发

在深入分析大型压水堆核电厂数字化仪表控制系统组合基础上,为与过程控制系统虚拟机软件并列应用,针对核安全控制系统进行虚拟仿真,研究开发基于Windows平台的数字化仪表控制系统(DCS)虚拟机软件VTXS。VTXS以自动代码分析和翻译转换为基本构建手段,以Visual C++为集成开发环境,采用面向对象模块化程序设计的方法、多线程和多进程通信的技术,以完全软件形式高逼真的再现真实TXS的安全控制功能。     

核电工程数据库系统的开发设计探讨

本文对核电工程数据库系统开发设计方面的问题进行了有益的探讨，并结合核工业总公司当前核电建设的实际需要，提出了一些具体的建设性意见，这对各成员单位的建库工作将有一定的协调、促进作用。     

核电厂企业内容管理信息系统建设

数据已逐渐成为企业可持续发展、提高决策水平和创新能力的战略性资源;企业数据量快速膨胀,并呈现出来源多样化和类型复杂化的特点,传统关系数据库管理系统（RDBMS）处理的结构化数据仅占数据信息总量的15%,而全球85%的信息是非结构化的。如何管理这些非结构化信息,成为传统结构化数据管理的一大难题,而企业内容管理系统恰好是解决这一问题的有效方式。文章通过分析国内部分核电企业内容管理系统现状,提出了企业内容管理系统选型方面的建议,从实际应用出发探讨了核电厂企业内容管理系统的建设。     

大亚湾核电站18个月换料工程及其项目管理

介绍了大亚湾核电厂在实施18个月换料改造中涉及到的各个方面。包括工程方案的确定、承包商的选定、项目的分解及实施情况、项目管理及风险控制方面的经验等等。并介绍了通过该项目成功实施技术引进，促进了长周期换料工程设计技术自主化和AFA 3G核燃料制造国产化。     

核电站电气系统采用微机监控系统的设想

论述核电站电气系统采用微机监控系统的必要性和可行性，提出了电气设备的计算机控制方式设想，并对其功能，可靠性和经济性做了说明和探讨。     

Seven-year temporal variation of Caesium-137 discharge inventory from the port of Fukushima Daiichi Nuclear Power Plant: continuous monthly estimation of Caesium-137 discharge in the period from April 2011 to June 2018

ABSTRACT

After direct discharges of highly contaminated water of the Fukushima Daiichi Nuclear Power Plant (1 F) from April to May 2011, Kanda suggested that relatively small amounts of run-off of radionuclides from the 1 F port into the Fukushima coastal region subsequently continued by his estimation method. However, the estimation period was limited to up to September 2012. Therefore, this paper estimatesthe discharge inventory up to June 2018. In the missing period, the Japanese government and Tokyo Electric Power Company Holdings have continued efforts to stop the discharge, and consequently, the radionuclide concentration in seawater inside the 1 F port has gradually diminished. We show the monthly discharge inventory of ¹³⁷Cs up to June 2018 by two methods, i.e., Kanda method partially improved by the authors and a more sophisticated method using Voronoi tessellation reflecting the increase in the number of monitoring points inside the 1 F port. The results show that the former always yields overestimated results compared with the latter, but the ratio of the former to the latter is less than one order of magnitude. Using these results, we evaluate the impact of the discharge inventory from the 1 F port into the coastal area and radiation dose upon fish ingestion.