Development and Application of Maintenance Template in Pressurized Water Reactor Nuclear Power Plant

Good practices of maintenance optimization in nuclear power field need to be effectively consolidated and inherited,and maintenance optimization can provide technology support to create a long-term reliable and economic operation for nuclear power plants( NPPs) especially for a large number of nuclear powers under construction. Based on the development and application of maintenance template in developed countries,and combining with reliability-centered maintenance( RCM) analysis results and maintenance experience data over the past ten years in domestic NPPs, the development process of maintenance template was presented for Chinese pressurized water reactor( PWR) NPP,and the application of maintenance template to maintenance program development and maintenance optimization combined with cases were demonstrated. A shortcut was provided for improving the efficiency of maintenance optimization in domestic PWR NPP,and help to realize a safe,reliable,and economic operation for domestic NPPs.

Case Study of Reactor Containment Building Construction in Nuclear Power Plant

It is very important to reduce the construction duration of the Reactor Containment Building (RCB) when considering the more than 50 months on average from concrete placement to completion. Through a case study, this study performs a pre-study for the reduction of construction duration in nuclear power plant project based on construction process of the RCB. The actual data of the case study have been collected and analyze the process and the external wall drawings of the RCB with construction practitioners. As a result of that, it is necessary to modularize the external wall form for equipment hatch and to extend the height of one layer of the external wall form to reduce the construction duration of RCB. The results of this study will be utilized to reduce construction duration of the nuclear power plant.

Proposal of a Deuterium-Deuterium Fusion/PWR Fission Hybrid Reactor

This article proposes to associate a Deuterium-Deuterium (D-D) fusion reactor with a PWR (fission Pressurized Water Reactor) in a hybrid reactor. Even if the mechanical gain (Q factor) of the D-D fusion reactor is below the unity and consequently consumes more energy than it supplies, due to the high energy amplification factor of the PWR fission reactor, the global yield is widely superior to 1. As the energy supplied by the fusion reactor is relatively low and as the neutrons supplied are mainly issued from D-D fusions (at 2.45 MeV), the problems of heat flux and neutrons damage connected with materials, as with D-T fusion reactors are reduced. Of course, there is no need to produce Tritium with this D-D fusion reactor. This type of reactor is able to incinerate any mixture of natural Uranium, natural Thorium and depleted Uranium (waste issued from enrichment plants), with natural Thorium being the best choice. No enriched fuel is needed. So, this type of reactor could constitute a source of energy for several thousands of years because it is about 90 more efficient than a standard fission reactor, such as a PWR or a Candu one, by extracting almost completely the energy from the fertile materials U238 and Th232. For the fission part, PWR technology is mature. For the fusion part, it is based on a reasonable hypothesis done on present Stellarators projects. The working of this reactor is continuous, 24 hours a day. In this paper, it will be targeted a reactor able to provide net electric power of about 1400 MWe, as a big fission power plant.

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the MCNPX code for analysing neutron behavior and the PARET/ANL code for understanding power variations, to get a clearer picture of the reactor’s performance. The analysis covers the initial six years of GHARR-1’s operation and includes projections for its whole 60-year lifespan. We closely observed the patterns of both the highest and average PPFs at 21 axial nodes, with measurements taken every ten years. The findings of this study reveal important patterns in power distribution within the core, which are essential for improving the safety regulations and fuel management techniques of the reactor. We provide a meticulous approach, extensive data, and an analysis of the findings, highlighting the significance of continuous monitoring and analysis for proactive management of nuclear reactors. The findings of this study not only enhance our comprehension of nuclear reactor safety but also carry significant ramifications for sustainable energy progress in Ghana and the wider global context. Nuclear engineering is essential in tackling global concerns, such as the demand for clean and dependable energy sources. Research on optimising nuclear reactors, particularly in terms of safety and efficiency, is crucial for the ongoing advancement and acceptance of nuclear energy.

Comparison of Risk Assessment for a Nuclear Power Plant Construction Project Based on Analytic Hierarchy Process and Fuzzy Analytic Hierarchy Process

Recently, plant construction throughout the world, including nuclear power plant construction, has grown significantly. The scale of Korea’s nuclear power plant construction in particular, has increased gradually since it won a contract for a nuclear power plant construction project in the United Arab Emirates in 2009. However, time and monetary resources have been lost in some nuclear power plant construction sites due to lack of risk management ability. The need to prevent losses at nuclear power plant construction sites has become more urgent because it demands professional skills and large-scale resources. Therefore, in this study, the Analytic Hierarchy Process (AHP) and Fuzzy Analytic Hierarchy Process (FAHP) were applied in order to make comparisons between decision-making methods, to assess the potential risks at nuclear power plant construction sites. To suggest the appropriate choice between two decision-making methods, a survey was carried out. From the results, the importance and the priority of 24 risk factors, classified by process, cost, safety, and quality, were analyzed. The FAHP was identified as a suitable method for risk assessment of nuclear power plant construction, compared with risk assessment using the AHP. These risk factors will be able to serve as baseline data for risk management in nuclear power plant construction projects.

Novel Technological Developments with Impacts on Perspectives for Mobile Nuclear Power Plants

New research developments suggest that nuclear reactors using fusion may enter the market sooner than imagined even for mobile applications, like merchant ship propulsion and remote power generation. This article aims at pointing such developments and how they could affect nuclear fusion. The method is enumerating the main nuclear reactors concepts, identifying new technological or theoretical developments useful to nuclear field, and analysing how new recombination could affect feasibility of nuclear fusion. New technologies or experimental results do not always work the way people imagine, being better or worse for intended effects or even bringing completely unforeseen effects. Results point the following designs could be successful, in descending order of potential: aneutronic nuclear reactions using lattice confinement, aneutronic nuclear reactions using inertial along magnetic confinement, hybrid fission-lattice confinement fusion, and fission reactions.

Analytical Architectural Study on Nuclear Power Plants

This paper aims to study the architectural design and components of Nuclear Power Plants （NPPs）. It is also focusing on the simulation system. Its main objective is to set general guidelines for architects. They should be aware of the basics of nuclear facilities designs and components. A traditional nuclear power plant consists of a nuclear reactor, a control building, a turbines building, cooling towers, service buildings （an office building ＆ a medical research center） and a nuclear ＆ radiation waste storage building. Bushehr nuclear power plant in Iran and Angra nuclear power plant in Brazil have been chosen as examples. Furthermore, this paper presents design analyses for Bushehr nuclear power plant and Angra nuclear power plant that include design theory （linear design and radial design） and positive ＆ negative aspects of these designs. At the end of this paper, results and recommendations on the architectural and urban aspects of nuclear power plants are revealed.

Project Construction and Important Technical Innovation for Qinshan Phase Ⅲ (PHWR) Nuclear Power Plant

Qinshan Phase Ⅲ(PHWR)Nuclear Power Plant,the first commercial heavy water reactor nuclear power plant in China,was the biggest trade project performed between the governments of China and Canada.As the owner,the Third Qinshan Nuclear Power Company(TQNPC)persisted in independent innovation management during the project construction,commissioning and self-dependent operation,efficiently realizing the three controls of the project,i.e.quality control,schedule control and investment control,and persisted in technical improvement on the basis of digestion and absorption of CANDU-6 technology to improve the unit safety and reliability.The project construction practice has helped China's nuclear power project management to becomeprogrammed,computerized,standardized and internationalized management from the existing basis.After completion of the project,with unit safe and steady operation as the prerequisite,TQNPC performed several technical modifications and innovations to continuously improve the unit performance.In the area of staff development,TQNPC paid much attention to cultivation of corporate culture,strengthed staff training and built up a good circulating mechanism with staff training and project construction promoting each other.Further to "Zero Breakthrough" and a new step forward of locolization successfully realized in Qinshan Nuclear Power Plant and Nuclear Power Qinshan Joint Venture Company,the improvement and developemnt of nuclear power project management level in Qinshan Phase Ⅲ(PHWR)Nuclear Power Plant provided reference for promotion of nuclear power development in China and standardized management of introducing large imported project.

Increases in Mortality for All Causes and All Cancers Combined before and after Startup of a Nuclear Power Plant in New Jersey, USA

The Salem/Hope Creek nuclear plant in southern New Jersey is one of just four U.S. plants with three large reactors (all others consist of one or two). These reactors started operations in 1976, 1980, and 1986 and routinely released toxic radioactive gases and particles into the environment. Only a single study has been performed by federal officials on cancer near nuclear plants—a study now 30 years old. A review of official mortality data using four-year periods shows the Salem County cancer death rate was consistently just below that of other New Jersey counties up to the mid-1980s. However, from 1983-1986 to 2015-2017, the county rate soared from -5.4% below the rest of the state to +32.6% above. The county/state mortality ratio for all causes also increased rapidly in these periods, from +0.6% above to +28.4% above the state. Salem now has the highest cancer death rate, and the 2nd highest total death rate of any New Jersey county. Had the 1983-1986 county-state ratios not changed in the following 31 years, 3493 fewer deaths (1018 of them from cancer) would have occurred among Salem County residents. The lack of any apparent etiologies that could have caused such a dramatic and unexpected change, plus the fact that the Salem/Hope Creek reactors are aging, corroding, and more prone to leaking radionuclides, emphasizes the immediate need for more studies of this type, and the inclusion of local health as a crucial factor in public decisions on the plant’s future.

Rising Thyroid Cancer Incidence Proximate to a New York City-Area Nuclear Power Plant

Thyroid cancer incidence has risen steadily in the US for several decades. While any cause of this trend has yet to be clearly identified, most analyses have concluded that there are factors other than improved detection accounting for the increase. Since exposure to radioactive iodine is the only acknowledged root cause of thyroid cancer, a review of temporal trends in incidence since the late 1970s near the Indian Point nuclear power plant, just 23 miles from the New York City border, was conducted. Rates in the four counties closest to Indian Point, where virtually the entire population resides within 20 miles of the plant, were compared with national trends in the US. The relative ratio in the local area was 0.778 in the period 1976-1981, or 22.2 percent lower than the national rate. This ratio increased steadily, to 1.579 (57.9 percent greater than the US) by the period 2000-2004, which slightly declined to 1.515 (51.5 percent greater) in the latest period available (2010-2014). Significant increases occurred for both males and females, and in each of the four counties. Annual new cases diagnosed among residents of the four counties increased from 51 to 412 between 1976-1981 and 2010-2014. Because the two large reactors at Indian Point began operations in 1973 and 1976, and exposures to radioiodine isotopes can manifest as cancer from five years to several decades after exposure, iodine emissions from Indian Point emissions should be considered as a potential factor in these trends. More studies near Indian Point and other nuclear installations should be conducted to further explore this potential association.

Feasibility Study of RNPP (Rooppur Nuclear Power Project) in Bangladesh

Bangladesh is densely populated country with a population of 16 core and small area about 1, 47,570 Square-Kilometer. Among these large population only a few section are taking the blessings of power. But now at a stage government can’t give the power even to that special section. Because day by day population is increasing and also power demands is also increasing. Governments are trying to meet up the power crisis in Bangladesh by taking various steps. Like small (10-20MW) power plants, IPP, Rental power plant etc. But these are not a permanent solution. More over these rental and IPP are mainly oil and gas based, which are very costly and not very efficient. Besides these government are going with coal based power station and small scale renewable energy. But coal based power station are required very large space, its initial cost is high and create serious environmental threat. Renewable energy is not yet developed and its efficiency is very poor. Though there are many problems and threats but Nuclear Power Plant can be a permanent solution for Bangladesh. Bangladesh government is now going for nuclear power plant and recently they have taken a project called Rooppur Nuclear Power Plant Project (RNPP) which is already approved in the cabinet meeting. The purpose of this paper is to study the feasibility of RNPP.

Prospects of Technological Improvement of Nuclear and Environmental Safety of World Energy

Today, the most urgent problem of the existing and future nuclear power industry is to ensure the nuclear and environmental safety of the operation of nuclear power reactor units (NPPs) and nuclear power plants (NPPs). It is solved thanks to the application of deeply echeloned protection and an anti-accident complex of methods and means for effective control of the operation of active reactor zones (AZR). However, the danger of existing NPPs in the world from time to time manifests itself in the form of severe post-project accidents and catastrophes with the release into the environment of a significant amount of radioactive materials dangerous for all living things. The results of the analysis show that the unconditional fulfillment of the main requirements of nuclear environmental safety and biocompatibility is possible only in the so-called wave nuclear reactor of the G-V generation, which, unlike reactors of the previous generations III, II+ and IV, does not require supercritical loading of the core with nuclear fuel. In the active zone of this reactor, nuclear-physical processes governed by physical law are implemented, which exclude the operator’s participation in regulating the reactivity of the reactor’s active zone, which makes it the reactor with the highest level of nuclear and environmental safety today, which is based on the principles of so-called internal safety, free from the human factor. The possibility of burning nuclear fuel based on U238 and Th232 in it expands the reserves of energetic nuclear fuel almost to inexhaustibility. The technology of nuclear reactors of the G5 generation through the secondary use of spent irradiated nuclear fuel (SNF) for the production of energy and energy raw materials with simultaneous burning of it to an environmentally safe state is able to quickly reduce the available stocks and further production of dangerous SNF, guarantee the nuclear and environmental safety of NPPs with reactors G5 and to technologically make nuclear post-project accidents and disasters impossible at the level of physical law with the complete elimination of the human factor.

国际可移动小型堆开发与运输安全研究现状

可移动小型堆(TNPPS)作为小型模块化反应堆(SMR)的一种(一般指30 MW以下的SMR),当通过陆路、海运等方式运输后在运输工具上或者从运输工具卸载后能够运行和产生电能,可以满足偏远、局部区域的供热、用电需求,引起了各国的重视。本文简要介绍了国际可移动小型堆发展现状,重点对国际上不同类型可移动小型堆的特点、可移动小型堆发展面临的问题和挑战进行总结,并重点讨论了可移动小型堆运输安全相关问题及对策建议。

核电站堆腔混凝土辐照试验研究

作为核电站关键材料的堆腔混凝土,其安全服役是核电站长期稳定安全运行的前提条件之一。为了进行堆腔混凝土的中子辐照损伤机理研究,获得堆腔混凝土在中子辐照环境下的试验数据,本文建立了堆腔混凝土辐照试验方法,研制了辐照试验装置,并在研究堆中对其进行了加速辐照试验。结果表明:辐照试验装置设计合理,辐照试验指标满足试验要求,实现了两种规格多个混凝土试样的中子辐照。进一步的混凝土试样辐照性能研究结果表明:混凝土试样在平均快中子注量3.41×10^(18) cm^(−2)下辐照后,与辐照前相比,其外部形状未见明显差异,但试样颜色变化较大,并且出现一定的辐照肿胀和力学性能退化现象。

热管冷却反应堆系统研究进展和挑战

热管是一种高效的非能动热量传递元件,热管冷却反应堆核动力系统在多场景特种应用领域具备独特优势。本文概述了热管冷却反应堆特种核动力系统发展情况。首先介绍了热管冷却反应堆概念提出以及在海陆空天等领域的应用场景分析,同时总结了国内外典型堆型的发展现状。其次探讨了当前热管冷却反应堆面临的关键技术挑战,包括高性能材料研究、高性能热管研制、高效能量转换技术研究、设计分析技术研究。最后对未来发展趋势进行了分析和展望,强调了整体系统一体化研制、发电器件特性研究以及智能自主控制技术在热管冷却反应堆领域的重要性。本文的系统性总结将推动热管冷却反应堆技术的进一步发展,为未来特种核动力系统的应用提供重要支持。

Variants of Nuclear Power Plants of Small and Medium Power with Heavy Liquid-Metal Coolants

New design solutions have been proposed for a BRS-GPG type reactor circuit, which are different from transport and stationary low and medium-powered reactor installations cooled with heavy liquid-metal coolants, and which correspond to the evolutionary development of such installations. While developing these solutions, the available experience in creating and operating Soviet pilot and commercial power plants cooled with lead-bismuth coolants was used, including investigations, primarily experimental ones, carried out by team of authors in justification of a capacity range (50 - 250 MW) of low and medium-powered reactor plants with horizontal steam generators (BRS- GPG) proposed and elaborated at the NNSTU.

基于两点模型的堆芯功率多目标保性能控制

现阶段能源产业需要核电站能够根据实际功率需求对输出功率进行调整,因此压水堆堆芯负荷跟踪运行是现阶段压水堆商业化运行的重要需求之一.为了避免运行过程中由于堆芯功率分布不均匀导致的氙震荡、热点等问题,对堆芯运行过程中产生的轴向功率偏差进行控制也是压水堆安全运行的关键.基于中子动力学方程、反应性反馈方程和热工水力学方程,结合堆芯功率空间耦合构建了压水堆堆芯功率两节点模型,并在这一模型的基础上增加负荷跟踪和轴向功率偏差跟踪量.根据这一模型设计了能够实现负荷跟踪控制和轴向功率分布控制并且具有抗时变性的LPV-LQR多目标控制器.在经典的多个瞬态工况下进行仿真的结果表明,LPV-LQR控制器具有良好的负荷跟踪控制和轴向功率分布控制能力,并且能够更好适应堆芯功率系统的时变性.

空间热管反应堆电源研究进展及展望

深空探测技术的发展对动力系统提出了更高的要求。传统的太阳能电源与化学电源的适用范围较小,环境适应能力不强,而微型核反应堆电源能量密度高,不依赖太阳光照,可应用于轨道运输、高轨探测多场景任务。在微型核反应堆电源技术路线中,热管冷却核反应堆电源因其系统设备极大简化、模块化设计,高可靠的全固态堆芯、非能动传热及瞬态响应迅速等特性,成为空间核反应堆电源最具可行性的路线之一。通过文献调研总结目前空间热管堆发展现状,从发展历史出发,梳理热管冷却核反应堆电源设计和理论研究,总结热管冷却核反应堆电源发展方向和关键技术。

铅基反应堆海洋核动力发展研究

铅基反应堆(铅基堆)核动力具有固有安全、小型轻量、长寿高效等突出优点,在先进海洋装备、无人潜航器、深海空间站的能源动力上应用前景广阔;在加快建设海洋强国的背景下,保障海洋能源供给成为重要的基础条件,开展铅基堆海洋核动力发展研究是推动我国海洋装备能源动力技术革新的关键内容。本文总结了海洋核动力的应用场景与发展需求,从技术特征、代表性应用、研制现状等方面系统梳理了铅基堆核动力的发展概况,凝练和剖析了包括核燃料与包壳材料、一回路关键设备、冷却剂工艺与氧测控、先进发电技术在内的铅基堆海洋核动力关键技术。立足国情研判了铅基堆海洋核动力面临的发展挑战,提出了低温铅基堆海洋核动力、高温高效铅基堆海洋核动力、一体化全自然循环铅基堆海洋核动力等可行技术路线。研究建议,强化前瞻性配套专项技术研发、加快部署装备示范工程,将铅基堆纳入重大能源战略、加快建设标准体系,设置国家级联合研发机构、构建科技创新和产业发展新模式,更好服务国家海洋战略并推动海洋核动力跨越式发展。

月面科研站核反应堆电源系统发展现状

伴随着月球科考与开发的全面展开,月面科研站的工程建设已逐渐提上日程,为月面科研站提供可靠、持续、长寿命的电力供应是先决条件。核反应堆电源系统,因适应月球各纬度地区和长昼夜交替条件,具有持续提供高功率输出、高能量密度和长寿命特点,被视为月面科研站能源系统主电源最有潜力的解决方案。本文首先总结了人类探月历史的演化,紧接着介绍了月面科研站能源系统面临的环境条件以及能源需求,然后介绍了月面核反应堆电源系统的结构和工作原理,并梳理了国内外当前各种月面科研站核反应堆电源系统的概念设计和开发阶段情况,最后对未来月面用核反应堆电源系统的发展前景进行了展望,并针对技术突破和应用需求提出了建议。