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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-st... 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 304Lrolling clad steel plate quenched and tempered simulated post-weld heat treatment property
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Numerical Investigation on Residual Stresses of the Safe-End/Nozzle Dissimilar Metal Welded Joint in CAP1400 Nuclear Power Plants 被引量:4
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作者 Wen-Chao Dong Dian-Bao Gao Shan-Ping Lu 《Acta Metallurgica Sinica(English Letters)》 SCIE EI CAS CSCD 2019年第5期618-628,共11页
The residual stress evolution in a safe-end/nozzle dissimilar metal welded joint of CAP1400 nuclear power plants was investigated in the manufacturing process by finite element simulation. A finite element model, incl... The residual stress evolution in a safe-end/nozzle dissimilar metal welded joint of CAP1400 nuclear power plants was investigated in the manufacturing process by finite element simulation. A finite element model, including cladding,buttering, post-weld heat treatment (PWHT) and dissimilar metal multi-pass welding, is developed based on SYSWELD software to investigate the evolution of residual stress in the aforementioned manufacturing process. The results reveal a large tensile axial residual stress, which exists at the weld zone on the inner surface, leads to a high sensitivity to stress corrosion cracking (SCC). PWHT process before dissimilar metal multi-pass welding process has a great in?uence on the magnitude and distribution of final axial residual stress. The risk of SCC on the inner surface of the pipe will increase if PWHT process is not taken into account. Therefore, such crucial thermal manufacturing process such as cladding, buttering and post-weld heat treatment, besides the multi-pass welding process, should be considered in the numerical model in order to accurately predict the distribution and the magnitude of the residual stress. 展开更多
关键词 cap1400 nuclear power plants NOZZLE Safe-end Dissimilar metal welding Residual stress
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CAP1400核电站屏蔽厂房结构特性与老化管理研究
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作者 吕阳 张永良 +1 位作者 方奇术 修振野 《全面腐蚀控制》 2023年第6期57-61,共5页
为了实现对CAP1400核电站屏蔽厂房的全寿命期间老化管理,在开展CAP1400核电站屏蔽厂房的结构特点分析和老化降质机理研究的基础上,详细分析了屏蔽厂房监检测技术和评估方法,并对CAP1400核电站的屏蔽厂房老化管理方法进行了探讨,为CAP140... 为了实现对CAP1400核电站屏蔽厂房的全寿命期间老化管理,在开展CAP1400核电站屏蔽厂房的结构特点分析和老化降质机理研究的基础上,详细分析了屏蔽厂房监检测技术和评估方法,并对CAP1400核电站的屏蔽厂房老化管理方法进行了探讨,为CAP1400核电站屏蔽厂房全寿命老化管理奠定基础。 展开更多
关键词 cap1400核电厂 屏蔽厂房 结构特性 老化管理
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CAP1400核电站接管和安全端焊接变形与残余应力研究 被引量:14
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作者 谷雨 张俊宝 余燕 《压力容器》 2016年第6期8-11,32,共5页
系统研究了CAP1400核电站接管和安全端模拟件焊接变形与残余应力分布特点。接管和安全端在焊接过程中焊接变形主要集中于焊接的初始阶段,焊接1/4厚度时,变形量为3 mm左右,焊接完成后,焊缝收缩量高达4.5 mm。盲孔法测试结果表明,在整个... 系统研究了CAP1400核电站接管和安全端模拟件焊接变形与残余应力分布特点。接管和安全端在焊接过程中焊接变形主要集中于焊接的初始阶段,焊接1/4厚度时,变形量为3 mm左右,焊接完成后,焊缝收缩量高达4.5 mm。盲孔法测试结果表明,在整个接管和安全端焊接接头内,环向与轴向焊接残余应力均为拉应力。焊接残余应力的最大值位于安全端镍基堆焊层与对接焊缝熔合线附近,测试结果达到500 MPa。 展开更多
关键词 cap1400核电站 接管和安全端 焊接变形 残余应力
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CAP1400示范电厂气载放射性流出物模拟计算
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作者 张琼 陈晓秋 +2 位作者 王博 张春明 郭瑞萍 《辐射防护》 CAS CSCD 北大核心 2016年第3期142-148,153,共8页
CAP1400为我国自行研发的装机容量为140万k W的先进非能动三代核电机组。本文以高斯烟羽模型为基础,介绍了我国自行设计的CAP1400核电站正常运行工况下气载排出物的弥散模式。针对实际情况,计算中对模型进行了相关修正,如有效源高、干... CAP1400为我国自行研发的装机容量为140万k W的先进非能动三代核电机组。本文以高斯烟羽模型为基础,介绍了我国自行设计的CAP1400核电站正常运行工况下气载排出物的弥散模式。针对实际情况,计算中对模型进行了相关修正,如有效源高、干湿沉积、放射性衰减等,结合示范电厂石岛湾厂址的气象数据,采用C-AIRDOS程序对气载放射性核素的大气弥散因子、年均浓度分布和部分核素的地面沉积浓度进行了模拟计算。为了解CAP1400示范核电厂运行后对周边地区的辐射环境影响提供了参考信息。 展开更多
关键词 cap1400 核电厂 大气弥散因子 空气浓度 地面沉积率
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CAP1400核电站SA738 Gr.B埋弧横焊工艺 被引量:2
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作者 董永志 于杰 樊祥博 《电焊机》 2019年第4期317-321,共5页
目前CAP1400核电站钢安全壳环缝(材料SA738 Gr.B)焊接以焊条电弧焊为主,效率低、成本高。在热处理和非热处理条件下进行埋弧横焊工艺试验,并对焊材适用性、试件制备要求、无损检测、机加工取样及破坏性试验结果进行分析。结果表明,采用... 目前CAP1400核电站钢安全壳环缝(材料SA738 Gr.B)焊接以焊条电弧焊为主,效率低、成本高。在热处理和非热处理条件下进行埋弧横焊工艺试验,并对焊材适用性、试件制备要求、无损检测、机加工取样及破坏性试验结果进行分析。结果表明,采用的焊材满足SA738 Gr.B钢板焊接技术要求,埋弧焊工艺稳定可靠,核电站钢安全壳筒体环缝可采用埋弧横焊工艺进行焊接。 展开更多
关键词 cap1400核电站 钢安全壳 环缝 埋弧横焊工艺
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