期刊文献+
共找到65篇文章
< 1 2 4 >
每页显示 20 50 100
Unit 1 of Ling’ao Nuclear Power Plant phase II underwent hot functional test successfully
1
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
下载PDF
Project Construction and Important Technical Innovation for Qinshan Phase Ⅲ (PHWR) Nuclear Power Plant 被引量:1
2
作者 Third Qinshan Nuclear Power Co.Ltd,CNNC(Haiyan County,Zhejiang Province,314300,China) 《工程科学(英文版)》 2007年第4期98-117,134,共21页
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 Thir... 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. 展开更多
关键词 Qinshan phase HEAVY Water REACTOR nuclear power plant project construction TECHNICAL INNOVATION
下载PDF
Supply contract for Nantong Power Plant Phase II signed
3
《Electricity》 1996年第3期45-45,共1页
Power generating equipment supply contract for Huaneng Nantong Power Plant Phase Ⅱ project affiliated to Huaneng International Electric Power Stock Company Ltd. was signed at the People’s Great Hall on June 28, 1996... Power generating equipment supply contract for Huaneng Nantong Power Plant Phase Ⅱ project affiliated to Huaneng International Electric Power Stock Company Ltd. was signed at the People’s Great Hall on June 28, 1996, Shi Dazhen, Minister of Electric Power, Ye Qing, Vice-chairman of the State Planning Commission, Zhang Youcai, Vice Minister of Finance and 展开更多
关键词 ii Supply contract for Nantong power plant phase ii signed
下载PDF
The third phase contract of Qinshan Nuclear Power Plant signed
4
《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
下载PDF
Some Technical Solutions for Environmental Protection System during Accidents at Nuclear Power Plants
5
作者 Sergey A. Kulyukhin Igor’ A. Rumer +5 位作者 Viktor M. Berkovich Gennadii S. Taranov Ivan V. Yagodkin Viktor P. Osipov Sergey S. Skvortsov Leo N. Falkovskii 《World Journal of Engineering and Technology》 2017年第4期1-11,共11页
The paper reports some technical solutions, which suggested or used for increasing of environmental protection during accidents at NPPs. For NNPs with two protective shells and pressure release system such as WWER-100... The paper reports some technical solutions, which suggested or used for increasing of environmental protection during accidents at NPPs. For NNPs with two protective shells and pressure release system such as WWER-1000 a comprehensive, passive-mode environmental protection system of decontamination of the radioactive steam-air mixture from the containment and the intercontainment area was suggested. This system includes the “wet” stage (scrubbers, etc.), the “dry” stage (sorption module), and also an ejector, which in a passive mode is capable of solving the multi-purpose task of decontamination of the air-steam mixture. For WWER-440/230 NPPs three protection levels: 1) a jet-vortex condenser;2) the spray system;3) a sorption module were suggested and installed. For modern designs of new generation NPPs, which do not provide for pressure release systems, a new passive filtering system together with the passive heat-removal system, which can be used during severe accidents in case all power supply units become unavailable, was proposed and after modernization was installed at the KudanKulam NPP (India). 展开更多
关键词 nuclear power plantS SEVERE ACCIDENT Environment Protection RADIOACTIVE Steam-Air phase
下载PDF
基于相变蓄冷的核电厂主控室非能动冷却系统
6
作者 赵丹 林宇清 吕胡人 《暖通空调》 2024年第1期1-4,30,共5页
为提高现有核电厂主控室紧急可居留系统的蓄冷能力及热舒适性水平,提出了基于定形相变蓄冷材料的核电厂主控室非能动冷却系统。基于主控室热负荷分布情况,该冷却系统在主控室顶板与吊顶之间、内墙面、地板底面及循环风道内,针对性地布... 为提高现有核电厂主控室紧急可居留系统的蓄冷能力及热舒适性水平,提出了基于定形相变蓄冷材料的核电厂主控室非能动冷却系统。基于主控室热负荷分布情况,该冷却系统在主控室顶板与吊顶之间、内墙面、地板底面及循环风道内,针对性地布置相应的含有定形相变材料的非能动冷却装置,进而实现事故工况下对主控室温度的精确控制。该非能动冷却系统无需引入额外冷源和管道,可靠性强,同时不破坏主体结构,且可灵活布置,解决了现有主控室非能动热阱时间余量小、热舒适性差的问题。 展开更多
关键词 核电厂 相变蓄冷 非能动冷却系统 主控室 应急可居留系统 定形相变材料
下载PDF
核电厂运行阶段安全文化评价指标体系研究
7
作者 李鹏程 许倩 王烨 《中国安全科学学报》 CAS CSCD 北大核心 2024年第2期60-66,共7页
为培育良好的核电厂运行阶段安全文化,通过分析核电厂运行特征,总结已有的核安全文化评价指标体系和评价模型,构建核电厂运行阶段安全文化评价指标体系,划分为价值观、行为、系统和环境4个层次,并细分出13个二级指标和61个三级指标;在... 为培育良好的核电厂运行阶段安全文化,通过分析核电厂运行特征,总结已有的核安全文化评价指标体系和评价模型,构建核电厂运行阶段安全文化评价指标体系,划分为价值观、行为、系统和环境4个层次,并细分出13个二级指标和61个三级指标;在此基础上,考虑到指标之间的非独立性和可能存在的相互影响关系,提出一种基于决策试验和评价实验法(DEMATEL)以及网络层次分析法(ANP)相结合的综合方法,确定指标体系的权重。结果表明:该方法结合调研数据,可得到核安全文化评价指标权重,并甄别出改善核安全文化的关键在于决策层的安全意识、以身作则等指标,为核电厂运行阶段安全文化的培育提供指导。 展开更多
关键词 核电厂 运行阶段 核安全文化 决策试验和评价实验法(DEMATEL) 网络层次分析法(ANP) 评价指标
下载PDF
Efects of thermal aging temperature and Cr content on phase separ-ation kinetics in Fe-Cr alloys simulated by the phase feld method 被引量:1
8
作者 Shu-xiao Li Hai-long Zhang +3 位作者 Shi-lei Li Yan-li Wang Fei Xue Xi-tao Wang 《International Journal of Minerals,Metallurgy and Materials》 SCIE EI CAS CSCD 2013年第11期1067-1075,共9页
Phase field simulations of phase separation in Fe-Cr binary alloys were performed by using the Cahn-Hilliard diffusion function. A new mobility model in relation to aging temperature and Cr content was used in the sim... Phase field simulations of phase separation in Fe-Cr binary alloys were performed by using the Cahn-Hilliard diffusion function. A new mobility model in relation to aging temperature and Cr content was used in the simulations. Two alloys of Fe-30at%Cr and Fe-35at%Cr were investigated at two different aging temperatures of 573 and 673 K. The phase separation kinetics was found to consist of three stages: wavelength modulation, amplitude increase, and coarsening of Cr-enriched regions. A higher thermal aging temperature accelerated the phase separation and increased the wavelength of concentration fluctuation. While the effect of Cr content on the phase separation kinetics was slight, Fe-Cr alloys with a higher Cr content were found to generate a larger number and a finer size of Cr-enriched regions. The simulation results provide consultation for design and safe operation of duplex stainless steel pipes in nuclear power plants. 展开更多
关键词 stainless steel duplex steel phase separation KINETICS nuclear power plants
下载PDF
Three Dimensional Numerical Analysis of Two Phase Flow Separation Using Swirling Fluidics
9
作者 M. M. Rahman Nobuatsu Tanaka +1 位作者 S. Yokobori S. Hirai 《Energy and Power Engineering》 2013年第4期301-306,共6页
Vapor-water two phase flow separation in pressure vessel of nuclear power plants is accomplished with swirl motion using vanes. In order to reduce separation pressure loss and to make it economic, a new type of low co... Vapor-water two phase flow separation in pressure vessel of nuclear power plants is accomplished with swirl motion using vanes. In order to reduce separation pressure loss and to make it economic, a new type of low cost simplified innovative separator using lattice core configuration is proposed where swirling is caused by the orthogonal driving flow. The performance of the separator has been assessed numerically with the commercial CFD code FLUENT 14.0. The numerical analysis is compared with the experiment. The geometry and flow conditions are chosen according to the experiment. In the analysis, standard k – e and realizable k – e turbulence models are implemented. The prediction of maximum air void fraction with realizable k – e model was almost the same as input air void fraction but the void fraction computed by standard k – e model was compared better with the experimental results than the realizable k – e model. Some discrepancies in flow pattern between the experimental and simulation results are observed which might be due to the difference of nozzle shape. However, a more detailed model is necessary to arrive at the final conclusion. 展开更多
关键词 Two phase Flow SEPARATION nuclear power plantS Swirling CFD
下载PDF
基于三次谐波电势分布特征的发电机定子绕组接地故障定位方法 被引量:4
10
作者 王义凯 尹项根 +2 位作者 谭力铭 乔健 朱凌进 《电工技术学报》 EI CSCD 北大核心 2023年第13期3552-3562,共11页
海洋核动力平台发电机拟采用有源电压消弧技术,需要实现全定子绕组内准确可靠的在线接地故障定位。针对现有基波定位方法存在的问题,该文提出一种基于三次谐波电势分布特征的发电机接地故障定位方法。基于各线圈三次谐波相电势180°... 海洋核动力平台发电机拟采用有源电压消弧技术,需要实现全定子绕组内准确可靠的在线接地故障定位。针对现有基波定位方法存在的问题,该文提出一种基于三次谐波电势分布特征的发电机接地故障定位方法。基于各线圈三次谐波相电势180°相带分布特点,构建三次谐波故障电势与三次谐波相电势间的几何关系式。以三次谐波故障电流为中间量,建立包含三次谐波故障电势、中性点三次谐波电压、中性点三次谐波电压变化量的解析定位方程。方程中不含接地过渡电阻,适用于未安装注入式保护设备的海洋核动力平台发电机。在工程应用中,该方法可与基波定位方法协同配合,解决基波定位方法的多解问题,并提高定位结果精度。仿真和动模试验结果验证了所提定位方法的准确性和有效性。 展开更多
关键词 海洋核动力平台 发电机定子绕组 接地故障定位 三次谐波 相带分布特点
下载PDF
核电站控制棒电源系统相复励发电机短路故障的解析计算 被引量:2
11
作者 肖项涛 郝亮亮 +1 位作者 王泽民 何鹏 《电力自动化设备》 EI CSCD 北大核心 2023年第11期124-132,共9页
针对核电站控制棒电源系统,现有保护仅采用以额定电流为定值的定时限过流保护作为短路后备保护,导致该系统已发生多起过流保护抢先动作与失磁保护失配的事件。解决保护失配问题的关键在于对控制棒电源系统发电机短路故障电流的准确解析... 针对核电站控制棒电源系统,现有保护仅采用以额定电流为定值的定时限过流保护作为短路后备保护,导致该系统已发生多起过流保护抢先动作与失磁保护失配的事件。解决保护失配问题的关键在于对控制棒电源系统发电机短路故障电流的准确解析,解析重点在于考虑发电机实际采用的相复励无刷励磁方式对故障电流的影响,而相复励励磁电流由并励电压对应的励磁分量和复励电流对应的励磁分量合成产生。经过合理的假设与模型简化,结合发电机基本方程和励磁系统数学模型,推导得到了并励电压分量作用下的三相短路电流。引入复励电流分量作用,根据励磁电流变化对短路电流进行修正,得到了包含暂态分量和稳态分量的相复励发电机三相短路电流时域解析表达式。由正序等效定则扩展得到两相短路电流的时域解析表达式。基于PSCAD/EMTDC平台建立了控制棒电源系统电磁暂态模型,对理论分析结果进行了验证,进一步对保护优化方法进行了讨论。 展开更多
关键词 核电站控制棒电源系统 相复励 发电机短路故障 故障解析
下载PDF
压水堆核电厂水锤机理及分析策略 被引量:1
12
作者 樊凯军 吕涛 +3 位作者 徐皎 张强 魏国军 张藤飞 《中国核电》 2023年第6期883-888,共6页
水锤事故在核电厂管路系统中经常发生,严重的水锤事故会引起爆管、拉断支撑并进一步引起机组停机停堆,严重威胁核电厂安全稳定运行。水锤不仅包括古典水锤,还包括汽锤以及与两相流有关的水锤。通过对水锤的基本类型的分析,给出了各种类... 水锤事故在核电厂管路系统中经常发生,严重的水锤事故会引起爆管、拉断支撑并进一步引起机组停机停堆,严重威胁核电厂安全稳定运行。水锤不仅包括古典水锤,还包括汽锤以及与两相流有关的水锤。通过对水锤的基本类型的分析,给出了各种类型水锤的避免建议,总结了压水堆核电厂水锤易发生部位和常见型式,提出了一种水锤事故的通用分析策略和水锤源初步辨识步骤,通过该辨识步骤可以迅速辨识压力波和有限长度水塞致水锤,并确定水锤源起始位置,有助于对核电厂中常见的疏水不畅导致的蒸汽推动水塞问题进行快速辨识。 展开更多
关键词 管道 水锤 汽锤 气液两相流 压水堆核电厂
下载PDF
核电高压给水加热器启动过程建模与仿真
13
作者 张志疆 田兆斐 《哈尔滨工程大学学报》 EI CAS CSCD 北大核心 2023年第12期2087-2094,共8页
为了研究金属材料的热惯性和温度变化速率对高压给水加热器启动过程的动态特性及能耗特性的影响,本文建立了基于两相非平衡模型的核电站高压给水加热器仿真模型。针对高压给水加热器的启动过程开展仿真研究,以抽汽阀门开度和给水焓值为... 为了研究金属材料的热惯性和温度变化速率对高压给水加热器启动过程的动态特性及能耗特性的影响,本文建立了基于两相非平衡模型的核电站高压给水加热器仿真模型。针对高压给水加热器的启动过程开展仿真研究,以抽汽阀门开度和给水焓值为入口扰动边界条件,分析了最大温度变化速率和正常温度变化速率下的启动过程动态特性。研究发现:高压给水加热器仿真模型完成启动后,壳侧压强、水位和给水出口温度等主要参数与设计值误差在1%以内;为了满足温度变化速率的限制,抽汽阀门开度变化率最快不能超过75.34%/h,正常变工况运行不得超过37.24%/h,对高压给水加热器的启动过程有重要指导意义。该仿真模型可以为高压给水加热器启动过程的调试和运行优化提供参考。 展开更多
关键词 高压给水加热器 启动过程 建模与仿真 动态特性 热惯性 温度变化速率 核电站 两相非平衡模型
下载PDF
Fault line selection in cooperation with multi-mode grounding control for the floating nuclear power plant grid 被引量:12
14
作者 Yikai Wang Xin Yin +3 位作者 Wen Xu Xianggen Yin Minghao Wen Lin Jiang 《Protection and Control of Modern Power Systems》 2020年第1期184-193,共10页
The Floating nuclear power plant grid is composed of power generation,in-station power supply and external power delivery.To ensure the safety of the nuclear island,the in-station system adopts a special power supply ... The Floating nuclear power plant grid is composed of power generation,in-station power supply and external power delivery.To ensure the safety of the nuclear island,the in-station system adopts a special power supply mode,while the external power supply needs to be adapted to different types of external systems.Because of frequent single phase-ground faults and various fault forms,the fault line selection protection should be accurate,sensitive and adaptive.This paper presents a fault line selection method in cooperation with multi-mode grounding control.Based on the maximum united energy entropy ratio(MUEER),the optimal wavelet basis function and decomposition scale are adaptively chosen,while the fault line is selected by wavelet transform modulus maxima(WTMM).For high-impedance faults(HIFs),to enlarge the fault feature,the system grounding mode can be switched by the multi-mode grounding control.Based on the characteristic of HIFs,the fault line can be selected by comparing phase differences of zero-sequence current mutation and fault phase voltage mutation before and after the fault.Simulation results using MATLAB/Simulink show the effectiveness of the proposed method in solving the protection problems. 展开更多
关键词 Floating nuclear power plant Multi-mode grounding control Wavelet transform modulus maxima(WTMM) Maximum united energy entropy ratio(MUEER) phase difference Single phase-ground fault
原文传递
核电厂辅助变压器进线回路断相监测方案研究
15
作者 魏巍 陈海龙 《核科学与工程》 CAS CSCD 北大核心 2023年第3期601-612,共12页
辅助变压器回路的断相故障监测是核电厂中最为关心的问题之一。断相故障可能会引起核电厂厂用电系统出现异常工况,例如母线电压不平衡、运行的设备跳闸、备用设备无法启动等。若核电厂在正常运行方式下,辅助变压器回路高压侧未能及时检... 辅助变压器回路的断相故障监测是核电厂中最为关心的问题之一。断相故障可能会引起核电厂厂用电系统出现异常工况,例如母线电压不平衡、运行的设备跳闸、备用设备无法启动等。若核电厂在正常运行方式下,辅助变压器回路高压侧未能及时检测到断相故障,一旦发电机母线失去电压需切换至厂外辅助电源供电,可能会导致关键的电动机跳闸,甚至是系统安全功能丧失,以致核电厂不能安全停堆。本文针对国内常用的辅助变压器方案提出了两种监测断相故障的方案,通过对断相监测方案的分析,并运用PSCAD/EMTDC软件建模仿真,分析出两种方案的特点,得出在针对核电厂不同的辅助变压器方案时,如何选择断相监测方案才能更准确、更有效的识别出断相故障。 展开更多
关键词 核电厂 辅助变压器 断相故障 监测方法
下载PDF
核电厂辅变空载运行期间辅助电源单相断相故障特征分析及应对措施
16
作者 魏巍 彭钰 《核科学与工程》 CAS CSCD 北大核心 2023年第3期686-694,共9页
目前,国内和国外的核电厂设计基准只考虑了电压完全丧失对于核电厂运行的影响,而忽略了断相故障对于核安全的挑战。辅助变压器在空载运行状态下发生断相故障时电气量十分微弱,因此如何检测并判别断相是核电厂中最为关心的问题。本文重... 目前,国内和国外的核电厂设计基准只考虑了电压完全丧失对于核电厂运行的影响,而忽略了断相故障对于核安全的挑战。辅助变压器在空载运行状态下发生断相故障时电气量十分微弱,因此如何检测并判别断相是核电厂中最为关心的问题。本文重点研究辅助变压器空载时的断相故障,结合对称分量法和变压器原理分析了辅助变压器空载运行状态下高压侧发生单相断相时的电气参数特征,运用ETAP软件建立了“华龙一号”核电厂厂用电系统仿真模型并进行了仿真分析。基于理论分析和仿真分析的结果,提出了辅助变压器空载时高压侧发生单相断相故障的应对措施,提高了厂外辅助电源的供电可靠性,有利于核电厂安全有序的运行。本文中辅助变压器空载状态下高压侧发生断相故障的电气参数特征研究分析结果对于辅助变压器断相保护方案的配置和断相保护设备的研发都具有指导意义。 展开更多
关键词 核电厂 辅助变压器 断相故障 电气参数特征 应对措施
下载PDF
核电厂辅助管道相控阵超声检测装置研制
17
作者 李杰 汪涛 +2 位作者 江小勇 许俊龙 李庚 《电力安全技术》 2023年第7期31-35,共5页
保证核安全是核电厂运营的重要工作,以核电厂一回路辅助管道热疲劳裂纹检测为研究对象,在对比检验对象的结构特点和国内外管道检测装置现状后,设计出一套适用于核电厂辅助管道的多种类、系列化的管道扫查装置,实现了核电厂辅助管道相控... 保证核安全是核电厂运营的重要工作,以核电厂一回路辅助管道热疲劳裂纹检测为研究对象,在对比检验对象的结构特点和国内外管道检测装置现状后,设计出一套适用于核电厂辅助管道的多种类、系列化的管道扫查装置,实现了核电厂辅助管道相控阵超声检测的实时显示和记录。 展开更多
关键词 核电厂 辅助管道 相控阵超声 检测装置
下载PDF
数字光学成像技术在岭澳核电厂的应用 被引量:6
18
作者 汪华安 左保成 +1 位作者 戴旭明 郑文棠 《地下空间与工程学报》 CSCD 北大核心 2009年第A02期1757-1762,共6页
介绍了数字光学成像技术在电力工程勘测应用中的适用性和优点,阐述了全景式钻孔电视成像系统的测试工作原理和工作流程,通过全景式钻孔摄像给出了全孔的孔壁展开图和三维虚拟岩芯图,对深层岩脉、节理、裂隙的产状和宽度进行量化统计,达... 介绍了数字光学成像技术在电力工程勘测应用中的适用性和优点,阐述了全景式钻孔电视成像系统的测试工作原理和工作流程,通过全景式钻孔摄像给出了全孔的孔壁展开图和三维虚拟岩芯图,对深层岩脉、节理、裂隙的产状和宽度进行量化统计,达到了定量分析钻孔节理裂隙几何特征的目的。应用数字光学成像技术于岭澳核电三期的边坡工程中,查明了边坡工程场区的主要岩层结构面和岩体完整性,通过对比常规勘测手段获得的节理裂隙发育规律,验证了全景式钻孔摄像的可靠性,表明该技术可较好地应用于核电工程中。 展开更多
关键词 数学光学成像 全景图像 三维虚拟岩芯图 岭澳核电厂
下载PDF
岭澳核电站二期反应堆核测量相关系统设计 被引量:7
19
作者 李文平 杨戴博 《核动力工程》 EI CAS CSCD 北大核心 2012年第2期1-4,共4页
分析岭澳核电站二期反应堆核测量各相关系统的主要特点,阐述核仪表系统(RPN)、堆芯中子注量率测量系统(RIC)、冷却剂丧失事故(LOCA)监测系统(LSS)与数字化仪表控制系统(DCS)的功能划分和接口设计方案。岭澳核电站二期设计方案针对RPN、... 分析岭澳核电站二期反应堆核测量各相关系统的主要特点,阐述核仪表系统(RPN)、堆芯中子注量率测量系统(RIC)、冷却剂丧失事故(LOCA)监测系统(LSS)与数字化仪表控制系统(DCS)的功能划分和接口设计方案。岭澳核电站二期设计方案针对RPN、RIC、LSS不同的功能需求和特点,有效地利用数字化仪表控制平台的优势,灵活采用3种与DCS的功能分配和接口划分方案,更好地实现了故障诊断和逻辑功能处理。 展开更多
关键词 岭澳核电站二期 核测量系统 功能分配 接口
下载PDF
秦山核电二期安全壳结构整体性试验 被引量:10
20
作者 赵树明 林松涛 王永焕 《工业建筑》 CSCD 北大核心 2003年第9期38-40,43,共4页
结合秦山核电二期 1RX安全壳结构整体性试验 ,介绍了其测试原理和方法 ,验收标准以及试验结果与分析。
关键词 秦山二期核电站 安全壳 整体性试验 测试 强度
下载PDF
上一页 1 2 4 下一页 到第
使用帮助 返回顶部