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IRRADIATION CREEP AND IRRADIATION STRESS RELAXATION OF 316 AND 304L STAINLESS STEEL

机译:316和304L不锈钢的辐照蠕变和辐照应力松弛。

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Irradiation creep and irradiation stress relaxation data have been obtained for CW316 SS, CW316LN SS and SA 304L SS. The measurements were performed on-line during irradiation. This is the first time that irradiation stress relaxation measurements have been performed by this technique, and the accuracy of the measurements reported in this study are better than previously used methods. The sample extension was observed to either decrease or increase when the reactor power, sample temperature, flux or stress changed This behavior only occurred when the power, temperature, flux or stress exceeded a threshold value. An initial shrinkage due to second phase precipitation/densification was observed for all of the materials tested. The standard CW 316 SS data confirmed the relationship between irradiation creep and irradiation stress relaxation for light water reactor applications. The irradiation creep of CW 316LN SS was a factor of 1.6 less than standard CW 316 SS. This reduction may possibly be explained by the decreased stacking fault energy of316LNSS relative to standard 316 SS. The irradiation creep in thermal neutron spectrum reactors was observed to be very different than values measured in fast neutron spectrum reactors. Therefore, fast reactor irradiation creep data are not recommended for application to light water reactors.
机译:已获得CW316 SS,CW316LN SS和SA 304L SS的辐照蠕变和辐照应力松弛数据。在辐照期间在线进行测量。这是首次通过这种技术进行辐照应力松弛测量,并且该研究报告的测量准确性比以前使用的方法更好。当反应堆功率,样品温度,通量或应力发生变化时,观察到样品延伸量减少或增加。这种现象仅在功率,温度,通量或应力超过阈值时发生。对于所有测试的材料,观察到由于第二相沉淀/致密化引起的初始收缩。标准的CW 316 SS数据证实了轻水反应堆应用中的辐射蠕变和辐射应力松弛之间的关系。 CW 316LN SS的辐照蠕变比标准CW 316 SS小1.6倍。相对于标准316 SS而言,316LNSS的堆垛层错能量降低可能可以解释这种减少。观察到热中子谱反应堆中的辐射蠕变与快速中子谱反应堆中测量的值有很大不同。因此,不建议将快速反应堆辐射蠕变数据应用于轻水反应堆。

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