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NEUTRON IRRADIATION CREEP AT 100°C ON 316L, AMCR, AND WELDED 316L STAINLESS STEEL ALLOYS

机译:在316L,AMCR和焊接316L不锈钢合金100°C时,中子照射蠕变

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We performed measurements on the elongation of many different austentic stainless steel alloys irradiating at 100°C in a low flux channel of the High Flux Reactor at Petten varying the applied stress between zero and 300 MPa. We irradiated in total 98 samples in two irradiation rigs. Of these samples only 26 samples could be tested up to a dose of 2.1 dpa, and 13 samples up to a dose of 0.21 dpa. The steels tested are listed in Table I. In the second irradiation rig four TIG-welded samples and one EB-welded sample were irradiated. We found that the length of the samples increased up to an irradiation dose of 0.11 dpa and then either decreased or increased slightly depending on the magnitude of the applied stress. We attributed the increase in length to the volume change due to the formation of carbides and to the accommodation of carbides to the applied stress. The decrease of the length with irradiation time is attributed to the formation of brittle α-ferrite. The amount of α-ferrite formed increases with decreasing irradiation temperature and increases with decreasing applied stress. Eight samples broke during irradiation in 8 columns or stems in two rigs before the first elongation test at 0.11 or 0.21 dpa could be performed. Irradiation of 343 samples of the same materials in the last fifteen years at temperatures between 300 and 500°C did not cause fracture.
机译:我们在高焊剂反应器的低通道通道中对许多不同的抛光不锈钢合金的伸长率进行了测量,在高磁通反应器的低通道处,在0和300MPa之间的施加应力下。我们在两种照射钻机中总共98个样品照射。这些样品仅26个样品可以测试高达2.1dPa的剂量,13个样品高达0.21dPa的剂量。测试的钢列于表I中。在第二辐射钻机中,照射了四个TIG焊接样品和一个EB焊接样品。我们发现样品的长度增加到0.11dPa的照射剂量,然后根据施加的应力的大小略微下降或略微增加。由于碳化物的形成以及碳化物的容纳,我们将长度的增加与体积变化的增加归因于施加的应力。用辐射时间的长度的减小归因于脆性α-铁素体的形成。形成的α-铁氧体的量随着辐射温度的降低而增加,随着施加的应力降低而增加。在0.11或0.21dPa的第一伸长率试验之前,在8个柱或茎中的辐射期间八个样品在8柱中突破,或者可以进行0.11或0.21dPa。在300至500°C之间的温度下,在过去的十五年中辐照相同材料的样品不会导致骨折。

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