Abstract
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 temperatures (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 desorption 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 fracture behaviour is a consequence of plasticity localization resulting from the interaction between DSA and hydrogen. HESIV and HELP are the dominant HE mechanisms.
| Original language | English |
|---|---|
| Article number | 153161 |
| Journal | Journal of Nuclear Materials |
| Volume | 556 |
| DOIs | |
| Publication status | Published - 1 Dec 2021 |
| MoE publication type | A1 Journal article-refereed |
Funding
The funding for the “SAFE-II” and “LEAD” projects from the Swiss Federal Nuclear Safety Inspectorate (ENSI) is gratefully acknowledged.
Keywords
- Dynamic strain ageing
- Hydrogen embrittlement
- Low-alloy steel
- Reactor pressure vessel
- Thermal desorption spectroscopy
Fingerprint
Dive into the research topics of 'Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver