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Evaluation of Irradiation Damage Effect by Applying Electric Properties BasedTechniques

机译:应用基于电特性的技术评估辐照损伤效果

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The pressure vessel of the reactor (RPV) in light water reactors (LWR) is a key component for the safe operation ofa nuclear power plant, being it part of the containment of the plant and non replaceable. Its life therefore largely delimits thelife of the plant.The most important effect of the degradation by radiation is the decrease in the ductility of the RPV ferritic steels.The main way to determine the mechanical behaviour of the RPV steels are tensile and Charpy impact tests, from which theductile to brittle transition temperature (DBTT) and its increase due to neutron irradiation can be calculated. These tests aredestructive and regularly applied to surveillance specimens to assess the integrity of RPV. The possibility of applyingvalidated non-destructive aging monitoring techniques would however facilitate the surveillance of the materials that formthe reactor vessel. On the one hand it would indeed allow in-situ inspection and on the other it would allow saving preciousspecimens for those surveillance programmes which have an insufficient amount of surveillance material available.The JRC-IAM has developed two devices, focussed on the measurement of the electrical properties to assess nondestructivelythe embrittlement state of materials. The first technique, called STEAM (Seebeck and Thomson Effects onAged Material), is based on the measurement of the Seebeck coefficient, characteristic of the material and related to themicrostructural changes induced by irradiation embrittlement. With the same aim the second technique, named REAM,measures instead the resistivity of the material.The purpose of these studies is to correlate the results of the Charpy tests, hardness, STEAM and REAMmeasurements with the change in the mechanical properties due to neutron irradiation. For this purpose different sets ofalloys coveting a large spectrum of steels have been used. The alloys are characterised with parametric variation of thecontent of impurities such Phosphorus, Copper, and Nickel, elements that are known to play a significant role in materialcharacteristic and degradation.The STEAM and REAM techniques have been successfully applied to the model alloys irradiated in the High FluxReactor of Petten (The Netherlands). The results of this study are shown in the paper and will enable a better understandingof the role and the influence of the above mentioned elements on the mechanical properties of steels. These results will makepossible the improvement of such techniques based on the measurement of material electrical properties for their applicationto the irradiation embrittlement assessment.
机译:轻水反应堆(LWR)中的反应堆压力容器(RPV)是核电厂安全运行的关键组件,因为它是电厂安全壳的一部分,并且不可更换。因此,它的寿命在很大程度上限制了设备的寿命。辐射降解的最重要影响是RPV铁素体钢的延展性下降。确定RPV钢力学性能的主要方法是拉伸和夏比冲击试验,从中可以计算出延展性至脆性转变温度(DBTT)及其由于中子辐照而引起的上升。这些测试具有破坏性,并定期应用于监视样本以评估RPV的完整性。然而,应用有效的非破坏性老化监测技术的可能性将促进对形成反应堆容器的材料的监测。一方面,它的确允许就地检查,另一方面,它可以为那些没有足够监视材料的监视程序节省宝贵的标本。JRC-IAM开发了两种设备,专注于测量电性能可无损评估材料的脆化状态第一种技术称为STEAM(老化材料的Seebeck和Thomson效应),基于Seebeck系数的测量,材料的特性,并与辐照脆化引起的微观结构变化有关。出于同样的目的,第二种技术,即REAM,代替了测量材料的电阻率。这些研究的目的是使夏比测试,硬度,STEAM和REAM测量的结果与中子辐照引起的机械性能变化相关联。 。为此目的,已经使用了令人垂涎的各种钢合金。合金的特征在于杂质(例如磷,铜和镍)的含量参数变化,这些杂质在材料的特性和降解中起着重要作用.STEAM和REAM技术已成功应用于高温辐照的模型合金中。 Petten的FluxReactor(荷兰)。该研究的结果显示在论文中,将使人们能够更好地理解上述元素的作用及其对钢的机械性能的影响。这些结果将可能基于对材料电性能的测量来改进此类技术,以将其应用于辐照脆性评估。

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