首页> 外文会议>13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 >THE INFLUENCE OF MECHANICAL DEFORMATION ON THE IRRADIATION CREEP OF AISI 316 STAINLESS STEEL IRRADIATED IN THE EBR-II AND FFTF FAST REACTORS
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THE INFLUENCE OF MECHANICAL DEFORMATION ON THE IRRADIATION CREEP OF AISI 316 STAINLESS STEEL IRRADIATED IN THE EBR-II AND FFTF FAST REACTORS

机译:机械变形对EBR-II和FFTF快速反应器辐照的AISI 316不锈钢辐照蠕变的影响

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Irradiation creep of stainless steels is thought not to be very responsive to material and environmental variables. To test this perception earlier unpublished experiments conducted in the EBR-II reactor on AISI 316 have been analyzed. While swelling is dependent on the cold-work level at 400-480°C, the post-transient irradiation creep rate, often called the creep compliance B_0, is not dependent on cold-work level. If the tube reaches pressures on reactor start-up that generate above-yield stresses in unirradiated steel, then plastic strains occur prior to significant irradiation, but the post-transient strain rate is identical to that of material that did not exceed the yield stress on start-up. It is shown that both stress-free and stress-affected swelling are isotropic and that the Soderberg relationship is maintained. At temperatures above ~540°C thermal creep and stored energy begin to assert themselves, with creep rates accelerating with cold-work and becoming non-linear with stress. These results are in agreement with a similar study on titanium-modified 316 steel in FFTF.
机译:据认为,不锈钢的辐照蠕变对材料和环境变量的响应不是很强。为了检验这种感觉,已经分析了在AISI 316上的EBR-II反应器中进行的较早未发表的实验。溶胀取决于400-480°C下的冷作水平,而瞬态辐射后的蠕变速率(通常称为蠕变柔量B_0)却不取决于冷作水平。如果管子达到反应堆启动时的压力,在未辐照的钢上产生高于屈服应力的应力,则在显着辐照之前会发生塑性应变,但瞬态后的应变率与未超过屈服应力的材料的瞬态应变率相同。启动。结果表明,无应力膨胀和受应力影响的膨胀都是各向同性的,并且保持了索德伯格关系。在高于540°C的温度下,热蠕变和存储的能量开始发挥作用,蠕变速率随着冷加工而加速,并随着应力变为非线性。这些结果与在FFTF中对钛改性316钢进行的类似研究相一致。

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