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核电压力容器用SA-508-3-1钢的冶炼 被引量:7
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作者 薛永栋 晋帅勇 +1 位作者 汪勇 郭彪 《大型铸锻件》 2012年第6期24-26,共3页
针对核电压力容器用SA-508-3-1钢的组织与性能特点,分析出冶炼的难点,通过对冶炼工艺的深入研究,提出了采用EBT初炼—LF精炼—真空脱气—真空浇注的冶炼工艺方案,按该工艺方案成功冶炼浇注了核电SA-508-3-1钢锭。经过锻造及热处理等工序... 针对核电压力容器用SA-508-3-1钢的组织与性能特点,分析出冶炼的难点,通过对冶炼工艺的深入研究,提出了采用EBT初炼—LF精炼—真空脱气—真空浇注的冶炼工艺方案,按该工艺方案成功冶炼浇注了核电SA-508-3-1钢锭。经过锻造及热处理等工序后,锻件性能达到核电压力容器锻件要求,并获得国家核安全局认证。 展开更多
关键词 sa-5083—1钢 冶炼 核电压力容器
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Mechanical and fatigue properties of SA508-Ⅳ steel used for nuclear reactor pressure vessels
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作者 Xin Dai Yue-feng Chen +3 位作者 Peng Wang Li Zhang Bin Yang Lian-sheng Chen 《Journal of Iron and Steel Research(International)》 SCIE EI CAS CSCD 2022年第8期1312-1321,共10页
The mechanical and fatigue properties of SA508-Ⅳ steel with martensite and granular bainite, respectively, were studied. The mechanical tests results showed that the ultimate tensile strength and impact toughness of ... The mechanical and fatigue properties of SA508-Ⅳ steel with martensite and granular bainite, respectively, were studied. The mechanical tests results showed that the ultimate tensile strength and impact toughness of the specimen with martensite were 830 MPa and 158 J, respectively, and those of the specimen with granular bainite were 811 MPa and 115 J, respectively. The former had higher tensile strength and impact toughness than the latter. The impact tests results showed that the former belonged to typical dimple fracture, while the latter belonged to brittle fracture. The fatigue tests results showed that the fatigue life of the specimen with martensite was 2717 cycles, and that of the specimen with granular bainite was 1545 cycles under the strain amplitude of ± 0.45%. The specimen with martensite had fewer crack initiation points, narrower fatigue striations separation, and larger volume fraction of high-angle grain boundaries than the latter. The fewer crack initiation points meant fewer fatigue cracks, the narrower fatigue striations separation meant slower crack propagation rate, and the larger volume fraction of high-angle grain boundaries could more effectively hinder fatigue crack propagation. Based on these facts, the fatigue life of the specimen with martensite was higher than that of the specimen with granular bainite. 展开更多
关键词 nuclear reactor pressure vessel sa508-steel Low cycle fatigue Crack initiation Crack propagation
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三代核电反应堆压力容器低合金钢焊缝性能对比分析
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作者 梅乐 张俊宝 +3 位作者 王永东 黄逸峰 王秉熙 郑明光 《压力容器》 北大核心 2024年第2期1-6,共6页
通过模拟国内三代核电压水堆反应堆压力容器环焊缝,分别采用国产焊接材料和进口焊接材料,在焊接工艺性能、焊缝金属化学成分、拉伸、冲击韧性、落锤和低周疲劳试验等方面进行了对比分析。结果表明,国产和进口焊接材料的焊接工艺性能和... 通过模拟国内三代核电压水堆反应堆压力容器环焊缝,分别采用国产焊接材料和进口焊接材料,在焊接工艺性能、焊缝金属化学成分、拉伸、冲击韧性、落锤和低周疲劳试验等方面进行了对比分析。结果表明,国产和进口焊接材料的焊接工艺性能和焊缝金属力学性能均相当;焊接试件不同厚度取样位置的焊缝金属-28.3℃冲击吸收能量平均值都大于90 J,有较大的设计裕量。该国产焊接材料已应用于国内某三代核电机组反应堆压力容器,为进一步推广应用提供技术支撑。 展开更多
关键词 反应堆压力容器 sa-508 Gr.3 Cl.1钢 国产焊材 焊缝性能
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Microscopic damage mechanism of SA508 Gr3 steel in ultra-high temperature creep
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作者 Zhi-gang Xie Yan-ming He +3 位作者 Jian-guo Yang Xiang-qing Li Chuan-yang Lu Zeng-liang Gao 《Journal of Iron and Steel Research(International)》 SCIE EI CAS CSCD 2018年第4期453-459,共7页
The lower head of reactor pressure vessel (RPV) will endure a great temperature gradient above the phase transition temperature, and the creep and fracture will be the primary failure mode for the RPV material in su... The lower head of reactor pressure vessel (RPV) will endure a great temperature gradient above the phase transition temperature, and the creep and fracture will be the primary failure mode for the RPV material in such a situation. The interrupted creep tests were performed on a typical RPV material, SA508 Gr3 steel, at 800 ℃. The microstructure of different creep stages was examined by scanning electron microscopy and transmission electron microscopy. The results showed that the microscopic damage is mainly induced by creep cavities and coarse second-phase particles. Furthermore, the volume fractions of creep cavities and coarse second-phase particles show a linear relationship with the extended creep time. The second-phase particles are determined to be MoC in the second creep stage and Mo2C in the third creep stage, according to the results of selected-area electron diffraction pattern. Combined with energy-dispersive spectrum analysis, the segregation of precipitates caused by the migration of atoms is finally unveiled, which leads to the coarsening of the particles. 展开更多
关键词 Reactor pressure vessel sa508 Gr3 steel In-vessel retention. Second-phase particle Damage mechanism Ultra-high temperature creep
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Effect of strain rate and temperature on the serration behavior of SA508-Ⅲ RPV steel in the dynamic strain aging process 被引量:1
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作者 Xue Bai Su-jun Wu +3 位作者 Li-jun Wei Shuai Luo Xie Xie Peter K. Liaw 《Journal of Iron and Steel Research(International)》 SCIE EI CAS CSCD 2018年第7期767-775,共9页
Dynamic strain aging (DSA) effect on SA508-III reactor pressure vessel (RPV) steel was investigated. The SA508-III RPV steel was subjected to tension tests at different strain rates (1.1× 10-5 s-1 and 6.6... Dynamic strain aging (DSA) effect on SA508-III reactor pressure vessel (RPV) steel was investigated. The SA508-III RPV steel was subjected to tension tests at different strain rates (1.1× 10-5 s-1 and 6.6× 10-5 s-1) and different temperatures (500 and 550 ℃) to evaluate the influence of strain rate and temperature on the serrated flow behavior, which is the repetitive and discontinuous yielding phenomenon on the stress-strain curves. The higher temperature leads to the higher density of precipitates, M23C6 carbides and needle-like Mo2C carbides. It was found that the samples under tension test of 6.6 × 10-5 s-1 and 500 ℃ possess superior mechanical properties and mainly show A-type serrations on the tension test curves. Then, the local regress method was used to filter the DSA curves, thus to show the real trend of the curves. It has been found that the less time of interaction between dislocations and precipitates under higher strain rates leads to a higher strength of the sample. The more tiny-stress drops on the 550 ℃ serration curve can be attributed to the hardening phase, M23C6 carbides and needle-like Mo2C carbides. The higher percentage of the small stress drops on the serration curves represents the higher mechanical strength. 展开更多
关键词 Reactor pressure vessel steel sa508- steel Dynamic strain aging Serration behavior
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反应堆压力容器用低合金钢焊接材料性能研究
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作者 梅乐 王永东 +1 位作者 张俊宝 宋波 《科技资讯》 2023年第24期116-118,共3页
SA-508Gr.3Cl.1低合金钢用埋弧焊焊丝焊剂主要用于三代核电反应堆压力容器等容器壳体的焊接。采用国产埋弧焊焊丝及焊剂,通过试板焊接和熔敷金属力学性能试验,研究了焊接电流和热输入对熔敷金属力学性能的影响,为国产焊材的工程应用提... SA-508Gr.3Cl.1低合金钢用埋弧焊焊丝焊剂主要用于三代核电反应堆压力容器等容器壳体的焊接。采用国产埋弧焊焊丝及焊剂,通过试板焊接和熔敷金属力学性能试验,研究了焊接电流和热输入对熔敷金属力学性能的影响,为国产焊材的工程应用提供了基础数据和技术支持。试验结果表明,在焊接热输入量为16364~29760 J/cm的范围内,国产埋弧焊焊丝焊剂熔敷金属在焊态和焊后热处理态的拉伸和冲击性能均满足设计要求,且有较大的裕量。 展开更多
关键词 反应堆压力容器 sa-508Gr.3Cl.1低合金钢 焊接材料 拉伸性能
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