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IRRADIATION INDUCED CHANGES IN MECHANICAL AND MICROSTRUCTURAL PROPERTIES OF THE HIGH FLUX REACTOR VESSEL: UPDATE OF THE RESULTS FROM 2014 AND 2015 SURVEILLANCE TEST CAMPAIGNS

机译:辐照导致高通量反应堆容器的机械和微观结构特性发生变化:2014年和2015年监测测试活动的结果更新

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The reactor vessel of the High Flux Reactor (HFR) in Petten has been fabricated from Al 5154 - O alloy grade with a maximum Mg content of 3.5 wt. %. The vessel experiences large amount of neutron fluences (notably at hot spot), of the order of 10~(27) n/m~2, during its operational life. Substantial damage to the material's microstructure and mechanical properties can occur at these high fluence conditions. To this end, a dedicated surveillance program: SURP (SURveillance Program) is executed to understand, predict and measure the influence of neutron radiation damage on the mechanical properties of the vessel material. In the SURP program, test specimens fabricated from representative HFR vessel material are continuously irradiated in two specially designed experimental rigs. A number of surveillance specimens are periodically extracted and tested to evaluate the changes in fracture toughness properties of the vessel as a function neutron fluence. The surveillance testing results of test campaigns performed until 2009 were already published by N. V. Luzginova et. al. [1]. The current paper presents results from the two recent surveillance campaigns performed in 2014 and 2015. The fracture toughness and tensile testing results are reported. Changes in mechanical properties of Al 5154-O alloy with an increase in neutron fluence are discussed in correlation with the irradiation damage microstructure observed in TEM and the fracture morphology observed in SEM. The HFR surveillance testing results are compared to the historically published results on irradiated aluminum alloys and conclusions about the evolution of embrittlement trends in relation with irradiation induced damage mechanisms in HFR vessel are drawn at the end.
机译:Petten中的高通量反应器(HFR)的反应器容器由Al 5154-O合金等级制成,最大Mg含量为3.5重量%。 %。该船舶在其运营寿命期间经历大量的中子流量(特别是在热点),约为10〜(27)毫升的顺序。在这些高流量条件下可能发生对材料的微观结构和机械性能的大量损害。为此,执行专用监测计划:SURP(监控程序)被执行以理解,预测和测量中子辐射损伤对容器材料的力学性能的影响。在SURP程序中,由代表性HFR血管材料制造的试样在两个专门设计的实验钻机中连续照射。周期性地提取并测试多种监测样本,以评估容器的断裂韧性特性作为功能中子流量的变化。在2009年之前进行的测试活动的监测测试结果已由N.V. Luzginova et出版。 al。 [1]。本文介绍了2014年和2015年最近进行的两个监视活动的结果。报告了骨折韧性和拉伸试验结果。 Al 5154-O合金的力学性能的变化与中子流量的增加,与TEM中观察到的辐照损伤微观结构相关,并且在SEM中观察到的断裂形态。将HFR监测检测结果与历史上公布的结果进行了比较,并在终结抗辐射诱导损伤机制方面的脆化趋势的演变的结论在末端抽取。

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