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Low cycle fatigue - strain control test data for P91 - sj material at 550 °C (specimen identifier S17-SAG2)

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DataCite Commons2023-10-20 更新2025-04-16 收录
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https://odin.jrc.ec.europa.eu/alcor/DOIDisplay.html?p_RN5=2570019
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The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. The design and assessment of welds is very important for the Design of nuclear components and hence of the Design Rules. The weld joint is one major weak zone of the structures and it should be introduced in the design rules to reduce the weld loading conditions. According to the statements above, the LEI has carried out Low Cycle Fatigue tests on single P91 metal specimen and P91 specimens with cross-section weld joint. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).

在可持续核能技术平台(Sustainable Nuclear Energy Technology Platform, SNE TP)框架下,欧洲可持续核能工业倡议(European Sustainable Nuclear Industrial Initiative, ESNII)2010-2012年实施计划为欧洲第四代核能原型堆(European Gen IV prototypes)的开工建设制定了极为紧凑的时间表:即LFR ETPP(欧洲技术试验厂)Myrrha将于2014年开工,SFR原型堆ASTRID将于2017年开工。相较于现有技术,第四代核能反应堆(GEN IV reactors)在更高运行温度及材料更高辐照损伤方面,给设计人员与科学家带来了新的挑战。在此框架下,MATTER(材料测试与规则)项目拟开展针对性明确的研究,以细致探究材料在第四代核能反应堆运行条件下的行为,并找出这些材料在相关反应堆应用中正确使用的准则。焊缝的设计与评估对于核部件设计及设计规则而言至关重要。焊接接头是结构的主要薄弱区域之一,应将其纳入设计规则以降低焊缝载荷条件。基于上述表述,LEI已针对单一P91金属试样及带有横截面焊接接头的P91试样开展了低周疲劳(Low Cycle Fatigue)测试。这些活动是在MATTER项目(资助协议编号:269706)框架下进行的。
提供机构:
European Commission JRC
创建时间:
2015-03-26
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