Rao, G S and Yagodzinskyy, Y and Que, Z and Spatig, P and Seifert, H-P (2021) Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels. Journal of Nuclear Materials, 556 .
|PDF - Published Version |
Restricted to NML users only. Others may use ->
Available under License Creative Commons Attribution Non-commercial No Derivatives.
Tensile tests in air with hydrogen pre-charged smooth specimens and slow strain rate tests with smooth and notched specimens in hydrogenated high-temperature water (HTW) at elevated tempera- tures (250 −288 °C) on low-alloy reactor pressure vessel (RPV) steels revealed a softening in strength and a pronounced reduction in ductility, where the magnitude of hydrogen embrittlement (HE) increased with the dynamic strain ageing (DSA) susceptibility of the RPV steels. In hydrogen pre-charged specimens and in hydrogenated HTW, shear dominated transgranular fracture by microvoid coalescence with increasing amounts of macrovoids, quasi-cleavage regions and secondary cracking were observed. Thermal desorp- tion spectroscopy showed an increase in the concentration of trapped hydrogen in high binding energy traps (vacancies & voids) induced by straining in DSA regime. The observed hydrogen effects on frac- ture behaviour is a consequence of plasticity localization resulting from the interaction between DSA and hydrogen. HESIV and HELP are the dominant HE mechanisms.
|Uncontrolled Keywords:||Hydrogen embrittlement; dynamic strain ageing; thermal desorption spectroscopy; low-alloy steel; reactor pressure vessel; high-temperature water; ; environmental degradation tensile behavior pipeline steel; dislocations; toughness; strength|
|Divisions:||Material Science and Technology|
|Deposited By:||Dr G Sudhakar Rao|
|Deposited On:||29 Jul 2021 10:16|
|Last Modified:||15 Nov 2021 12:42|
Repository Staff Only: item control page