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

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-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 languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems
Subtitle of host publicationWater Reactors
PublisherSpringer
Pages1077-1099
Number of pages23
ISBN (Electronic)978-3-030-04639-2
ISBN (Print)978-3-030-04638-5
DOIs
Publication statusE-pub ahead of print - 7 Oct 2017
MoE publication typeA4 Article in a conference publication
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States
Duration: 18 Aug 201922 Aug 2019

Publication series

SeriesMinerals, Metals and Materials Series
ISSN2367-1181

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
CountryUnited States
CityBoston
Period18/08/1922/08/19

Fingerprint

Light water reactors
Steel structures
Aging of materials
Water
Heat affected zone
Structural integrity
Pressure vessels
Fracture mechanics
Strain rate
Hydrogen
Welds
Metals
Plastics
Temperature
Microstructure

Keywords

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

Cite this

Que, Z., Seifert, H. P., Spätig, P., Sudhakar, R. G., & Ritter, S. (2017). 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, 2017. pp. 1077-1099 (Minerals, Metals and Materials Series).
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Que, Z, Seifert, HP, Spätig, P, Sudhakar, RG & Ritter, S 2017, 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, 2017. p. 1077-1099 (Minerals, Metals and Materials Series).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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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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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. 2017. p. 1077-1099. (Minerals, Metals and Materials Series). https://doi.org/10.1007/978-3-030-04639-2_68