Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels

G. S. Rao, Y. Yagodzinskyy, Zaiqing Que (Corresponding Author), P. Spätig, H. P. Seifert

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)


    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 languageEnglish
    Article number153161
    JournalJournal of Nuclear Materials
    Publication statusPublished - 1 Dec 2021
    MoE publication typeA1 Journal article-refereed


    • Dynamic strain ageing
    • Hydrogen embrittlement
    • Low-alloy steel
    • Reactor pressure vessel
    • Thermal desorption spectroscopy


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