Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels

Zaiqing Que; Hans Peter Seifert; Philippe Spätig; Rao G. Sudhakar; Stefan Ritter

doi:10.1007/978-3-030-04639-2_68

Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels

Zaiqing Que^*
, Hans Peter Seifert
, Philippe Spätig
, Rao G. Sudhakar
, Stefan Ritter

^*Corresponding author for this work

Not published at VTT

Paul Scherrer Institute (PSI)

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

Abstract

The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems
Subtitle of host publication	Water Reactors
Publisher	Springer
Pages	1077-1099
ISBN (Electronic)	978-3-030-04639-2
ISBN (Print)	978-3-030-04638-5
DOIs	https://doi.org/10.1007/978-3-030-04639-2_68
Publication status	Published - 2019
MoE publication type	A4 Article in a conference publication
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: 18 Aug 2019 → 22 Aug 2019

Publication series

Series	Minerals, Metals and Materials Series
ISSN	2367-1181

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Country/Territory	United States
City	Boston
Period	18/08/19 → 22/08/19

Funding

Funding for the SAFE-II project from the Swiss Federal Nuclear Safety Inspectorate (ENSI) is gratefully acknowledged.

Keywords

Dynamic strain aging
Environmental assisted cracking
Fracture resistance reduction
Hydrogen embrittlement
Low alloy steel

Access to Document

10.1007/978-3-030-04639-2_68

Cite this

Que, Z., Seifert, H. P., Spätig, P., Sudhakar, R. G., & Ritter, S. (2019). Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors (pp. 1077-1099). Springer. https://doi.org/10.1007/978-3-030-04639-2_68

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title = "Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels",

abstract = "The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) \& EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.",

keywords = "Dynamic strain aging, Environmental assisted cracking, Fracture resistance reduction, Hydrogen embrittlement, Low alloy steel",

author = "Zaiqing Que and Seifert, \{Hans Peter\} and Philippe Sp{\"a}tig and Sudhakar, \{Rao G.\} and Stefan Ritter",

note = "Publisher Copyright: {\textcopyright} 2019, The Minerals, Metals \& Materials Society.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

year = "2019",

doi = "10.1007/978-3-030-04639-2\_68",

language = "English",

isbn = "978-3-030-04638-5",

series = "Minerals, Metals and Materials Series",

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address = "Germany",

}

Que, Z, Seifert, HP, Spätig, P, Sudhakar, RG & Ritter, S 2019, Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. in Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Springer, Minerals, Metals and Materials Series, pp. 1077-1099, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 18/08/19. https://doi.org/10.1007/978-3-030-04639-2_68

Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. / Que, Zaiqing; Seifert, Hans Peter; Spätig, Philippe et al.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Springer, 2019. p. 1077-1099 (Minerals, Metals and Materials Series).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels

AU - Que, Zaiqing

AU - Seifert, Hans Peter

AU - Spätig, Philippe

AU - Sudhakar, Rao G.

AU - Ritter, Stefan

PY - 2019

Y1 - 2019

N2 - The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.

AB - The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.

KW - Dynamic strain aging

KW - Environmental assisted cracking

KW - Fracture resistance reduction

KW - Hydrogen embrittlement

KW - Low alloy steel

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DO - 10.1007/978-3-030-04639-2_68

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AN - SCOPUS:85064066141

SN - 978-3-030-04638-5

T3 - Minerals, Metals and Materials Series

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BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems

PB - Springer

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Que Z, Seifert HP, Spätig P, Sudhakar RG, Ritter S. Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Springer. 2019. p. 1077-1099. (Minerals, Metals and Materials Series). Epub 2017 Oct 7. doi: 10.1007/978-3-030-04639-2_68

Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels

Abstract

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Keywords

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