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

G. S. Rao; Y. Yagodzinskyy; Z. Que; P. Spätig; H. P. Seifert

doi:10.1016/j.jnucmat.2021.153161

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

G. S. Rao, Y. Yagodzinskyy, Z. Que^*, P. Spätig, H. P. Seifert

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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.

Alkuperäiskieli	Englanti
Artikkeli	153161
Sivumäärä	13
Julkaisu	Journal of Nuclear Materials
Vuosikerta	556
Varhainen verkossa julkaisun päivämäärä	4 heinäk. 2021
DOI - pysyväislinkit	https://doi.org/10.1016/j.jnucmat.2021.153161
Tila	Julkaistu - 1 jouluk. 2021
OKM-julkaisutyyppi	A1 Julkaistu artikkeli, soviteltu

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10.1016/j.jnucmat.2021.153161Lisenssi: CC BY-NC-ND

ENG_Rao_et_al_Study_on_hydrogen_embrittlement_Journal_of_Nuclear_MaterialsFinal published version, 4,38 MBLisenssi: CC BY-NC-ND

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@article{7a1569bb94114c79a9ef1cb7641a361f,

title = "Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels",

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.",

keywords = "Dynamic strain ageing, Hydrogen embrittlement, Low-alloy steel, Reactor pressure vessel, Thermal desorption spectroscopy",

author = "Rao, {G. S.} and Y. Yagodzinskyy and Z. Que and P. Sp{\"a}tig and Seifert, {H. P.}",

note = "Funding Information: The funding for the “SAFE-II” and “LEAD” projects from the Swiss Federal Nuclear Safety Inspectorate (ENSI) is gratefully acknowledged. The authors would like to express their gratitude for the experimental contributions and helpful suggestions from S. Ritter, H. Kottmann, B. Baumgartner, R. Schwenold and D. Stammbach from Paul Scherrer Institut. Publisher Copyright: {\textcopyright} 2021 The Author(s)",

year = "2021",

month = dec,

day = "1",

doi = "10.1016/j.jnucmat.2021.153161",

language = "English",

volume = "556",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier Science B.V.",

}

TY - JOUR

T1 - Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels

AU - Rao, G. S.

AU - Yagodzinskyy, Y.

AU - Que, Z.

AU - Spätig, P.

AU - Seifert, H. P.

N1 - Funding Information: The funding for the “SAFE-II” and “LEAD” projects from the Swiss Federal Nuclear Safety Inspectorate (ENSI) is gratefully acknowledged. The authors would like to express their gratitude for the experimental contributions and helpful suggestions from S. Ritter, H. Kottmann, B. Baumgartner, R. Schwenold and D. Stammbach from Paul Scherrer Institut. Publisher Copyright: © 2021 The Author(s)

PY - 2021/12/1

Y1 - 2021/12/1

N2 - 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.

AB - 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.

KW - Dynamic strain ageing

KW - Hydrogen embrittlement

KW - Low-alloy steel

KW - Reactor pressure vessel

KW - Thermal desorption spectroscopy

UR - http://www.scopus.com/inward/record.url?scp=85109582359&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2021.153161

DO - 10.1016/j.jnucmat.2021.153161

M3 - Article

AN - SCOPUS:85109582359

SN - 0022-3115

VL - 556

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

M1 - 153161

ER -

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

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