首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels
【24h】

Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels

机译:隔离辐射诱发的偏析在奥氏体不锈钢的辐射辅助应力腐蚀开裂中的作用

获取原文
获取原文并翻译 | 示例
           

摘要

Post-irradiation annealing was used to help identify the role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (IASCC) by preferentially removing dislocation loop damage from proton-irradiated austenitic stainless steels while leaving the RIS of major and minor alloying elements largely unchanged. The goal of this study is to better understand the underlying mechanisms of IASCC. Simulations of post-irradiation annealing of RIS and dislocation loop microstructure predicted that dislocation loops would be removed preferentially over RIS due to both thermodynamic and kinetic considerations. To verify the simulation predictions, a series of post-irradiation annealing experiments were performed. Both a high purity 304L (HP-304L) and a commercial purity 304 (CP-304) tainless steel alloy were irradiated with 3.2 MeV protons at 360 degreesC to doses of 1.0 and 2.5 dpa. Following irradiation, post-irradiation anneals were performed at temperatures ranging from 400 to 650 degreesC for times between 45 and 90 min. Grain boundary composition was measured using scanning transmission electron microscopy with energy-dispersive spectrometry in both as-irradiated and annealed samples. The dislocation loop population and radiation-induced hardness were also measured in as-irradiated and annealed specimens. At all annealing temperatures above 500 C, the hardness and dislocation densities decreased with increasing annealing time or temperature much faster than RIS. Annealing at 600 C for 90 min removed virtually all dislocation loops while leaving RIS virtually unchanged. Cracking susceptibility in the CP-304 alloy was mitigated rapidly during post-irradiation annealing, faster than RIS, dislocation loop density or hardening. That the cracking susceptibility changed while the grain boundary chromium composition remained essentially unchanged indicates that Cr depletion is not the primary determinator for IASCC susceptibility. For the same reason, the visible dislocation microstructure and radiation-induced hardening are also not sufficient to cause IASCC alone. (C) 2002 Elsevier Science B.V. All rights reserved. [References: 38]
机译:辐照后退火用于通过优先去除质子辐照奥氏体不锈钢的位错环损伤,同时保留主要和次要的RIS,从而帮助确定辐照偏析(RIS)在辐照辅助应力腐蚀裂纹(IASCC)中的作用合金元素基本不变。这项研究的目的是更好地了解IASCC的潜在机制。 RIS的辐照后退火和位错环微观结构的模拟预测,由于热力学和动力学方面的考虑,位错环将比RIS优先去除。为了验证模拟预测,进行了一系列辐照后退火实验。高纯304L(HP-304L)和商业纯304(CP-304)不锈钢合金均在360℃下用3.2 MeV质子辐照,辐照剂量为1.0和2.5 dpa。辐照后,辐照后退火在400至650摄氏度的温度下进行45至90分钟。使用具有能量色散光谱的扫描透射电子显微镜在辐照和退火样品中测量晶界组成。还测量了辐照和退火试样的位错环总数和辐射诱导的硬度。在高于500 C的所有退火温度下,硬度和位错密度随退火时间或温度的增加而降低,远快于RIS。在600°C下退火90分钟,实际上消除了所有位错环,而使RIS几乎保持不变。 CP-304合金的裂纹敏感性在辐照后退火过程中迅速降低,比RIS,位错环密度或硬化更快。裂纹敏感性在晶界铬组成基本保持不变的情况下发生了变化,这表明Cr的消耗不是IASCC敏感性的主要决定因素。出于同样的原因,可见位错的微观结构和辐射诱导的硬化也不足以单独导致IASCC。 (C)2002 Elsevier Science B.V.保留所有权利。 [参考:38]

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号