首页> 外文会议>NATO Advanced Research Workshop on Hydrogen Recycling at Plasma Facing Materials Sep 15-19, 1999, St. Petersburg, Russia >AN INTERACTION OF HYDROGEN ISOTOPES WITH AUSTENITIC Cr - Ni STEELS WITHOUT AND DURING REACTOR IRRADIATION Hydrogen Recycle At Plasma Facing Materials
【24h】

AN INTERACTION OF HYDROGEN ISOTOPES WITH AUSTENITIC Cr - Ni STEELS WITHOUT AND DURING REACTOR IRRADIATION Hydrogen Recycle At Plasma Facing Materials

机译:反应器辐照过程中氢同位素与奥氏体Cr-Ni钢的相互作用及在反应器辐照期间氢的再循环。

获取原文
获取原文并翻译 | 示例

摘要

Experimental data on an interaction of hydrogen isotopes (protium and deuterium) with austenitic Cr - Ni steels are reported. The data were obtained with the special equipment designed and installed at the research reactor IVV -2M in the conditions without and during irradiation by fast neutrons of a flux density up to 1.8 X 10 ~(18)n/m~2s ( E > 0.lMeV), fluence up to 10~(25)n/m~2 and a gamma - absorbed dose rate< 3.6 W/g, a hydrogen pressure being up to 2.4 MPa. Steel samples were tested out - of - pile in the protium medium under static and dynamic modes, reaching the pressure of 50 MPa and rupture of the samples. The experimental data showed that the radiation effects increased with a decreasing temperature during irradiation. Thus, at T < 673 K a relative increase of both hydrogen permeability and solubility values can reach several orders of magnitude. Besides, there were observed the substantial deviations of isotopic effects, changing of physico -mechanical properties and other radiation effects.
机译:报告了氢同位素(pro和氘)与奥氏体Cr-Ni钢相互作用的实验数据。数据是通过在研究堆IVV -2M上设计并安装的特殊设备在无中子辐照的条件下和在辐照条件下进行的,其通量密度高达1.8 X 10〜(18)n / m〜2s(E> 0 (1MeV),注量高达10〜(25)n / m〜2,γ吸收剂量率<3.6 W / g,氢气压力高达2.4 MPa。钢样品在dynamic介质中以静态和动态模式进行桩外测试,达到50 MPa的压力并破裂。实验数据表明,辐射过程中辐射效应随温度的降低而增加。因此,在T <673 K时,氢渗透性和溶解度值的相对增加可以达到几个数量级。此外,还观察到了同位素效应,物理力学性质的变化和其他辐射效应的重大偏差。

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