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首页> 外文会议>20th International Symposium on Effects of Radiation on Materials, Jun 6-8, 2000, Williamsburg, Virginia >Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel
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Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel

机译：304不锈钢中的辐射诱发的偏析和空隙膨胀

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摘要

Void swelling and radiation-induced segregation have been measured in 304 stainless steel. Samples were irradiated in the outer regions of the EBR-II reactor where displacement rates of 2.0X10~(-8) and 6.6 X10~(-8) dpa/s are comparable to those in pressurized water reactor components. Samples were irradiated at temperatures from 371-390℃ to total doses of up to 20 dpa. Void swelling reached a maximum of 2 % at 20 dpa. Nickel enrichment and chromium depletion to of 20 at% and 12 at% respectively were measured. Both void swelling and radiation-induced segregation were dependent on dose rate, increasing as the dose rate decreased. Grain boundary compositions were measured both near and in areas free of precipitates. The presence of a precipitate significantly changes the grain boundary compositions near the precipitate.
机译：空隙膨胀和辐射引起的偏析已在304不锈钢中进行了测量。在EBR-II反应器的外部区域照射样品，其位移速率为2.0X10〜（-8）dpa / s和6.6 X10〜（-8）dpa / s，与压水反应堆组件中的位移速率相当。样品在371-390℃的温度下辐照至总剂量达20 dpa。空隙膨胀在20 dpa时最大达到2％。测得的镍富集和铬耗竭分别为20 at％和12 at％。空洞膨胀和辐射引起的偏析都取决于剂量率，随着剂量率的降低而增加。在附近和没有沉淀的区域都测量了晶界成分。析出物的存在显着改变了析出物附近的晶界组成。

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