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Application of the Seebeck effect for the monitoring of neutron embrittlementand low-cycle fatigue in nuclear reactor technology

机译:塞贝克效应在核反应堆技术中子脆性和低周疲劳监测中的应用

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The monitoring of neutron embrittlement and low-cycle fatigue in nuclear reactor steel is an important topic inlifetime extension of nuclear power plants. We therefore investigated the application of the Seebeck effect for determiningmaterial degradation of common reactor pressure vessel (RPV) steel. The Seebeck coefficients (SC) of several irradiatedCharpy specimens made from Japanese JRQ-steel were measured. The specimens suffered a fluence from 0 up to4.5 E19 neutrons per cm2 with energies higher than 1MeV.The measured changes of the SC within this range were about 500 nV, increasing continuously in the range underinvestigation. Some indications of saturation appeared at fluencies larger than 4.5 E19 neutrons per cm2. We obtaineda linear dependency between the SC and the temperature shift . T41 of the Charpy energy vs. Temperature curve which iswidely used to characterize material embrittlement. Similar measurements were performed on specimens made from theaustenitic stainless steel X6CrNiTi18-10 (according to DIN 1.4541) that were fatigued by applying a cyclic strain amplitudeof 0.28%.Further investigations were made to quantify the size of the gauge volume in which the termoelectric power isgenerated. It appeared that the information gathered from a (_T)hermo (_E)lectric (_P)ower (TEP) measurement is very local.To overcome this problem we propose a novel TEP-method using a (_T)hermoelectric (_S)canning (_M)icroscope (TSM).Icroscope We finally conclude that the change of the SC has a potential for monitoring of material degradation due to neutronirradiation and thermal fatigue, but it has to be taken into account that several influencing parameters could contributeto the TEP in either an additional or extinguishing manner. A disadvantage of the method is the requirement of aclean surface without any oxide layer. This disadvantage can partially be avoided by using the proposed new TSM.
机译:核反应堆钢中的中子脆化和低周疲劳的监测是核电厂寿命延长的重要课题。因此,我们研究了塞贝克效应在确定普通反应堆压力容器(RPV)钢的材料降解方面的应用。测量了几个由日本JRQ钢制成的辐射夏比试样的塞贝克系数(SC)。样品的通量从0到4.5 E19中子/ cm2,能量高于1MeV。在该范围内测得的SC变化约为500 nV,在调查不足的范围内不断增加。当通量大于每平方厘米4.5个E19中子时,出现了一些饱和迹象。我们得到了SC和温度漂移之间的线性关系。夏比能量-温度曲线的T41,广泛用于表征材料脆化。对由奥氏体不锈钢X6CrNiTi18-10(根据DIN 1.4541)制成的试样进行了类似的测量,这些试样通过施加0.28%的循环应变幅度而疲劳了,并进行了进一步研究以量化产生热电势的标尺体积的大小。似乎从(_T)hermo(_E)电(_P)ower(TEP)测量中收集的信息非常局部。为克服此问题,我们提出了一种使用(_T)热电(_S)罐装(我们最终得出结论,SC的变化具有监测由于中子辐照和热疲劳而引起的材料降解的潜力,但必须考虑到两个因素都可能会影响TEP中的TEP一种额外的或扑灭的方式。该方法的缺点是要求清洁的表面没有任何氧化物层。通过使用建议的新TSM可以部分避免此缺点。

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