HYDROGEN EMBRITTLEMENT CHARACTERISTICS IN IRRADIATED STAINLESS STEEL

被引：0
作者：
Khalil, Sarah [1 ,2 ]
Hatem, Tarek M. [3 ]
机构：
[1] British Univ Egypt, Fac Energy & Environm Engn, Cairo Suez Rd, El Sherouk City Cairo 11837, Egypt
[2] Alexandria Univ, Fac Engn, Alexandria, Egypt
[3] British Univ Egypt, Fac Energy & Environm Engn, Ctr Simulat Innovat & Adv Mfg, Cairo Suez Rd, El Sherouk City Cairo 11837, Egypt
来源：
PROCEEDINGS OF THE ASME 2020 INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, IMECE2020, VOL 12 | 2020年
关键词：
Stainless steel; hydrogen embrittlement; hydrogen trapping; irradiation; and cluster dynamics; SEGREGATION; DIFFUSION; IRON; GROWTH; METALS;
D O I：
暂无
中图分类号：
TP39 [计算机的应用];
学科分类号：
081203 ; 0835 ;
摘要：
Hydrogen is produced in nuclear reactors as a by-product of the corrosion reaction between the pressure vessel and the cooling water, where hydrogen produced may enter the metal in atomic form. During operation a reactor vessel is exposed to avalanche of neutron irradiation fluxes, in addition to corrosion from cooling water. A novel cluster dynamics model that accounts for off-stoichiometry of clusters and matrix was developed and applied to investigate the clustering behavior of Hydrogen-vacancy and Hydrogen-interstitial clusters in proton irradiated stainless steel has been developed. The differences in point defect migration energies and binding energy of H to lattice defects, makes it possible to have vacancy and interstitial clusters having compositions different from those of pure iron. The model predicts populations of Defect-Hydrogen complexes in iron The model is applied to the early stage formation of voids and dislocation loops in stainless steel in the presence of atomic hydrogen. This study investigates the effect of irradiation dose and temperature on the concentration of vacancy-Hydrogen (VmHn) and Intersitial Fe-H (FemHn) complexes on bulk alpha-Iron. The re
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页数：7
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