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

Z. 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

Z. Que (Corresponding author), Hans Peter Seifert, Philippe Spätig, Rao G. Sudhakar, Stefan Ritter

Not published at VTT

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
Number of pages	23
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	United States
City	Boston
Period	18/08/19 → 22/08/19

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

Link to publication in Scopus

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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. Minerals, Metals and Materials Series https://doi.org/10.1007/978-3-030-04639-2_68

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

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

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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, Z. (Corresponding author); Seifert, Hans Peter; Spätig, Philippe; Sudhakar, Rao G.; Ritter, Stefan.

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

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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.

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KW - Fracture resistance reduction

KW - Hydrogen embrittlement

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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). https://doi.org/10.1007/978-3-030-04639-2_68