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PSA study of the effect of extreme snowfall on a floating nuclear power plant:case study in the Bohai Sea
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作者 Lan‑Xin Gong Qing‑Zhu Liang Chang‑Hong Peng 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第11期212-225,共14页
This study presents a probabilistic safety analysis(PSA)method for the external event of extreme snowfall on a floating nuclear power plant(FNPP)deployed in the Bohai Sea.We utilized the Weibull and Gumbel extreme val... This study presents a probabilistic safety analysis(PSA)method for the external event of extreme snowfall on a floating nuclear power plant(FNPP)deployed in the Bohai Sea.We utilized the Weibull and Gumbel extreme value distributions to fit the collected meteorological data and obtained a hazard curve for the event of an extreme snowfall where the FNPP is located,providing a basis for the frequency of extreme snowfall-initiating events.Our analysis indicates that extreme snowfall primarily affects the ventilation openings of the equipment,leading to the failure of devices such as the diesel generators.Additionally,extreme snowfall can result in a loss of off-site power(LOOP).Therefore,the developed extreme snowfall PSA model is mainly based on the LOOP event tree,considering responses such as snowfall removal by personnel.Our calculations indicate a core damage frequency(CDF)of 1.13×10^(-10) owing to extreme snowfall,which is relatively low.The results of the cut-set analysis indicate that valve failures in the core makeup tank(CMT),passive residual heat removal system(PRS),and in-containment refueling water storage tank(IRWST)significantly contribute to the CDF. 展开更多
关键词 Floating nuclear power plant(FNPP) ACP100 Extreme snow PSA External hazard
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Development and Research of Non⁃Stirring Conveying Device for Waste Resin in Nuclear Power Plant
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作者 Jianfa Li Yongzhen Hua +2 位作者 Mingmei Liu Rui Zhang Taishan Lou 《Journal of Harbin Institute of Technology(New Series)》 CAS 2023年第3期45-59,共15页
Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transp... Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transport concentration and easy blockage of conveying equipment and pipelines in nuclear power plants in China,a set of non⁃stirring conveying devices is developed,and theoretical calculations,simulation analysis and experimental verification are carried out.By transporting resin using the no stirring conveying device developed in this paper,it is not only to eliminate the risk of blockage and ensure the safety of transportation,but also to adjust the concentration of conveying resin to change the transport efficiency according to the operating conditions.The effective bearing rate of waste resin storage tank can be improved,so that the comprehensive performance of waste resin storage and transportation in nuclear power plants can be greatly improved. 展开更多
关键词 nuclear power plant ion exchange resin TRANSPORTATION no stirring device no blockage
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Development of SA-533 Type B CL. 1+SA-240 Type 304L roll-bonded clad steel plate for safety injection tank of CAP1400 nuclear power plant 被引量:2
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作者 HOU Hong ZHANG Hanqian +1 位作者 YUAN Xiangqian DING Jianhua 《Baosteel Technical Research》 CAS 2017年第1期18-25,共8页
Aiming to meet the demand of the country's nuclear demonstration project on the CAP1400 nuclear power plant,Baosteel uses the roll-bonding technology and develops the SA-533 Type B CL. 1+SA-240 Type 304L high-stre... Aiming to meet the demand of the country's nuclear demonstration project on the CAP1400 nuclear power plant,Baosteel uses the roll-bonding technology and develops the SA-533 Type B CL. 1+SA-240 Type 304L high-strength and high-toughness clad steel plate with a shear strength of over 310 MPa for the nuclear power plant's safety injection tank. The properties of the quenched and tempered and the simulated post-weld heat treatment states are systematically studied herein through a comprehensive inspection and evaluation of the composition,microstructure,and properties of the clad steel plate. The results show that the bonding interface has high shear strength and that the base metal has high strength and good toughness at low temperatures. Hence,the performance fully meets the technical requirements of the CAP1400 nuclear power plant's safety injection tank in the country's nuclear demonstration project. The roll-bonded clad steel plate can be used to manufacture the safety injection tank of the CAP1400 nuclear power plant. 展开更多
关键词 CAP1400 nuclear power plant safety injection tank SA-533 Type B CL. 1+SA-240 Type 304L rolling clad steel plate quenched and tempered simulated post-weld heat treatment property
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Development and Application of Maintenance Template in Pressurized Water Reactor Nuclear Power Plant 被引量:2
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作者 张圣 陈宇 +1 位作者 曹智鹏 莫春铌 《Journal of Donghua University(English Edition)》 EI CAS 2015年第1期162-165,共4页
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 econom... 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. 展开更多
关键词 pressurized water reactor(PWR) nuclear power plant maintenance template maintenance program maintenance optimization
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Comparison of Risk Assessment for a Nuclear Power Plant Construction Project Based on Analytic Hierarchy Process and Fuzzy Analytic Hierarchy Process 被引量:6
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作者 Dae-Woong Shin Yoonseok Shin Gwang-Hee Kim 《Journal of Building Construction and Planning Research》 2016年第3期157-171,共15页
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 sin... 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. 展开更多
关键词 COMPONENT Analytic Hierarchy Process (AHP) Fuzzy Analytic Hierarchy Process (FAHP) nuclear power plant Reactor Containment Building (RCB) Risk Assessment
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Novel Technological Developments with Impacts on Perspectives for Mobile Nuclear Power Plants 被引量:1
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作者 Luciano Ondir Freire Delvonei Alves de Andrade 《World Journal of Nuclear Science and Technology》 2021年第4期141-158,共18页
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... 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. 展开更多
关键词 Fusion Reactors Mobile nuclear power plants nuclear Reactors nuclear Merchant Ships Clean Energy
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Effects of Liaoning Hongyanhe Nuclear Power Plant on the Zooplankton Community in Summer of 2017
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作者 WANG Junjian TAO Zhencheng +3 位作者 WANG Yantao WEI Hao LIU Xin LI Chaolun 《Journal of Ocean University of China》 SCIE CAS CSCD 2020年第5期1140-1152,共13页
To evaluate the effects of the Hongyanhe Nuclear Power Plant on the zooplankton community in the surrounding seawater during summer, multiple environmental factors and zooplankton distribution along the east coast of ... To evaluate the effects of the Hongyanhe Nuclear Power Plant on the zooplankton community in the surrounding seawater during summer, multiple environmental factors and zooplankton distribution along the east coast of Liaodong Bay were investigated in the summer of 2017. In particular, the influences of seawater temperature, salinity, and chlorophyll a(Chl a) on the zooplankton community were analyzed. Zooplankton abundances and Chl a concentrations along the east coast of Liaodong Bay showed an initial increase followed by a decrease from July to September. During the three months, the zooplankton abundance was the highest(8116.70 ind m^(-3)) in August. The Shannon-Wiener index showed a downtrend from July to September, with the average value falling from 1.65 in July to 1.50 in September. Calanus sinicus, Paracalanus parvus, copepodid, and bivalve larvae were the dominant species/groups in the three months. The effects of the nuclear power plant's outlet on the environment factors were mainly reflected in the increased seawater temperature. Redundancy analysis showed that the zooplankton community was jointly affected by seawater temperature, salinity and Chl a concentration, and the degree of this impact varied monthly. The impact of seawater temperature on the zooplankton community was stronger than that of salinity. The primary impact of the Hongyanhe Nuclear Power Plant on the structure and distribution of the zooplankton community in the surrounding seawater during the summer was increased seawater temperature, which caused a reduction in the abundance of dominant species/groups. 展开更多
关键词 ZOOPLANKTON ABUNDANCE community structure DIVERSITY environmental factor Hongyanhe nuclear power plant
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Size-dependent spatio-temporal dynamics of eukaryotic plankton community near nuclear power plant in Beibu Gulf,China
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作者 Lizhou LIN Haifeng GU +1 位作者 Zhaohe LUO Na WANG 《Journal of Oceanology and Limnology》 SCIE CAS CSCD 2021年第5期1910-1925,共16页
Pico-and nano-eukaryotic plankton are important members of marine ecosystems.To understand their community structure and spatio-temporal variations in the Beibu Gulf,and to study the impact of Changjiang Nuclear Power... Pico-and nano-eukaryotic plankton are important members of marine ecosystems.To understand their community structure and spatio-temporal variations in the Beibu Gulf,and to study the impact of Changjiang Nuclear Power Plant(CNPP)located in the northwest coast of the Hainan Island on the eukaryotic plankton,we studied these issues in the coastal water near CNPP bimonthly from February 2018 to January 2019 via 18 S Illumina sequencing.The results reveal a higher genetic alphadiversity and less beta-diversity of the plankton community in small-size(0.45-5μm and 5-20μm)fractions than in large-size(20-200μm and>20μm)fractions.The small-sized phytoplankton,including Micromonas(Chlorophyta)and Minutocellus(Bacillariophyta),as well as heterotrophic plankton,including Paraphysomonas(Chrysophyceae),Ellobiopsis(Dinoflagellates),and Syndiniales(Dinoflagellates),took up a considerable proportion in eukaryotic plankton community.In addition,it showed a slight temperature increase and no significant difference in eukaryotic plankton community between the outfall of CNPP and other sampling sites,suggesting that the impact of the thermal discharge from the CNPP on local eukaryotic plankton community was limited. 展开更多
关键词 nuclear power plant the Beibu Gulf eukaryotic plankton community high-throughput sequencing PICOPLANKTON NANOPLANKTON
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A framework for nuclear power plant emergency response system
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作者 Wang-kun CHEN 《Nuclear Science and Techniques》 SCIE CAS CSCD 2010年第6期375-378,共4页
The purpose of this study is to establish an intelligent expert system for nuclear power plant emergency response.A new framework of environmental risk management methodology by the concept of pattern recognition was ... The purpose of this study is to establish an intelligent expert system for nuclear power plant emergency response.A new framework of environmental risk management methodology by the concept of pattern recognition was introduced in this paper.A knowledge-based decision support system for emergency response and risk management of nuclear power plant was also discussed.The mathematical pattern relationship of accidental release effects on neighboring area and the corresponding response measures were presented in this paper.With this decision system,the decision maker can specify the procedure and minimize their human error in the decision process.The improvement of risk response and the quality of management system could be upgraded by this system.Besides,the methodology can also be served as a basis for the future development of environmental risk response system design. 展开更多
关键词 Expert system Emergency response Risk management nuclear power plant
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Decomposition of oil cleaning agents from nuclear power plants by supercritical water oxidation
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作者 Shi-Bin Li Xiao-Bin Xia +2 位作者 Qiang Qin Shuai Wang Hong-Jun Ma 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第4期83-95,共13页
Oil cleaning agents generated from nuclear power plants(NPPs)are radioactive organic liquid wastes.To date,because there are no satisfactory industrial treatment measures,these wastes can only be stored for a long tim... Oil cleaning agents generated from nuclear power plants(NPPs)are radioactive organic liquid wastes.To date,because there are no satisfactory industrial treatment measures,these wastes can only be stored for a long time.In this work,the optimization for the supercritical water oxidation(SCWO)of the spent organic solvent was investigated.The main process parameters of DURSET(oil cleaning agent)SCWO,such as temperature,reaction time,and excess oxygen coefficient,were optimized using response surface methodology,and a quadratic polynomial model was obtained.The determination coefficient(R^(2))of the model is 0.9812,indicating that the model is reliable.The optimized process conditions were at 515 C,66 s,and an excess oxygen coefficient of 211%.Under these conditions,the chemical oxygen demand removal of organic matter could reach 99.5%.The temperature was found to be the main factor affecting the SCWO process.Ketones and benzene-based compounds may be the main intermediates in DURSET SCWO.This work provides basic data for the industrialization of the degradation of spent organic solvents from NPP using SCWO technology. 展开更多
关键词 Supercritical water oxidation Oil cleaning agent nuclear power plants Response surface methodology
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Reliability-Centered Maintenance-Based Maintenance Decision in New Nuclear Power Plants
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作者 黄立军 陈宇 +1 位作者 马沂荩 吴进 《Journal of Donghua University(English Edition)》 EI CAS 2016年第2期248-251,共4页
Taking the project of introducing reliability-centered maintenance( RCM) into maintenance decision in an AP1000 nuclear power plant( NPP) under construction as the research object,an improved RCM methodology was propo... Taking the project of introducing reliability-centered maintenance( RCM) into maintenance decision in an AP1000 nuclear power plant( NPP) under construction as the research object,an improved RCM methodology was proposed, and the application software and an RCM-based maintenance strategies management system were designed. In the pilot project,the RCMbased maintenance decision methodology had been applied to determining the maintenance strategies for two systems. Both the decision process and the results were described in this paper. The achievements of this project promoted the introduction and routinization of an advanced and effective maintenance decision mode in nuclear power field,which could provide valuable reference for new NPPs in China. 展开更多
关键词 reliability-centered maintenance(RCM) maintenance strategy maintenance decision maintenance program nuclear power plant(NPP)
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Unit 1 of Ling’ao Nuclear Power Plant phase II underwent hot functional test successfully
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作者 Liu Chunsheng 《Electricity》 2010年第2期8-,共1页
On February 25, the Unit 1 of Ling’ao Nuclear Power Plant phase II underwent a 41-day-long hot functional test successfully with its major systems satisfying the requirements for
关键词 II TEST ao nuclear power plant phase II underwent hot functional test successfully Unit 1 of Ling
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Daya Bay Nuclear Power plant put under maintenance
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《Electricity》 1996年第1期54-54,共1页
The Daya Bay Nuclear Power Plant in South China’s Guangdong Province began its second refueling and maintenance work for its Unit 1 on March 31, 1996. Apart from the regular work required by the plant’s annual check... The Daya Bay Nuclear Power Plant in South China’s Guangdong Province began its second refueling and maintenance work for its Unit 1 on March 31, 1996. Apart from the regular work required by the plant’s annual check- up plan, all of the present guide tubes of the control rods in Unit I will be replaced by the type of state-of-the-art tubes used in Unit 2, to make the dropping-time of the tubes more accurate. The annual check may take 80 days, thus the unit will probably re-connect with the power grid in mid June. As for Unit 2, the "exciter" of generator malfunctioned during the start of the reactor on March 6, when the second refueling and maintenance neared completion. 展开更多
关键词 BAY WORK Daya Bay nuclear power plant put under maintenance
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Preliminary design for inland nuclear power plants completed
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作者 Liu Chunsheng 《Electricity》 2010年第2期7-,共1页
The State Nuclear Power Technology Corporation (SNPTC), which is responsible for the development of third-generation nuclear power technology in China, has completed the preliminary designs
关键词 Preliminary design for inland nuclear power plants completed CAP
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Ling'ao Nuclear Power Plant is well under way
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《Electricity》 1998年第4期9-9,共1页
关键词 WELL Ling’ao nuclear power plant is well under way
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The third phase contract of Qinshan Nuclear Power Plant signed
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《Electricity》 1996年第4期49-49,共1页
China and Canada nailed down a deal to build the third phase of the Qinshan Nuclear Power Plant in Zhejiang Province in East China on Nov. 26, 1996. The contract was signed in Shanghai by China National Nuclear Corp (... China and Canada nailed down a deal to build the third phase of the Qinshan Nuclear Power Plant in Zhejiang Province in East China on Nov. 26, 1996. The contract was signed in Shanghai by China National Nuclear Corp (CNNC) and Atomic Energy of Canada Ltd(AECL). AECL will construct two 700 MW heavy water reactors for the Chinese nuclear power plant. 展开更多
关键词 DOWN The third phase contract of Qinshan nuclear power plant signed
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Ling'ao Nuclear Power Plant is progressing as scheduled
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《Electricity》 1996年第3期5-5,共1页
Construction of Ling’ao Nuclear Power Plant in Guangdong Province, the country’s second-largest nuclear power project between 1996-2000, chalked up notable progress this year. On July, 15, all foreign suppliers in t... Construction of Ling’ao Nuclear Power Plant in Guangdong Province, the country’s second-largest nuclear power project between 1996-2000, chalked up notable progress this year. On July, 15, all foreign suppliers in the project were given official notice that both sides should start to implement the contracts. "The move marked a significant step forward in the project’s construction," said Zeng Wenxing, General Manager of Ling’ ao Nuclear Power Co Ltd, set up in 展开更多
关键词 BAY Ling’ao nuclear power plant is progressing as scheduled
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Daya Bay Nuclear Power Plant passed the State's check and acceptance
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《Electricity》 1997年第1期50-50,共1页
关键词 BAY Daya Bay nuclear power plant passed the State’s check and acceptance
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Variants of Nuclear Power Plants of Small and Medium Power with Heavy Liquid-Metal Coolants
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作者 Tatiana Alexandrovna Bokova Alexander Georgievich Meluzov +2 位作者 Pavel Andreevich Bokov Nikita Sergeevich Volkov Alexander Romanovich Marov 《Open Journal of Microphysics》 2021年第4期53-71,共19页
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 w... 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 So</span><span>viet pilot and commercial power plants cooled with lead-bismuth coolants</span><span> was used, including investigations, primarily experimental ones, carried out by team of authors in justification of a capacity range (50</span></span><span> </span><span>-</span><span> </span><span>250 MW) of low and medium-powered reactor plants with horizontal steam generators (BRS-</span><span> </span><span>GPG) proposed and elaborated at the NNSTU. 展开更多
关键词 Heavy Liquid Metal Coolant (HLMC) nuclear power plant Lead LEAD-BISMUTH Low and Medium power Reactor Steam Generator Solution Main Circulation Pump Solution BRS-GPG Multifunctional Reactor
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The first domesticated large-sized nuclear power plant was built up
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《Electricity》 2001年第4期52-52,共1页
关键词 The first domesticated large-sized nuclear power plant was built up
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