Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels

Zaiqing Que; Hans-Peter Seifert; Philippe Spätig; A. Zhang; J. Holzer; G. S. Rao; S. Ritter

Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels

Zaiqing Que, Hans-Peter Seifert, Philippe Spätig, A. Zhang, J. Holzer, G. S. Rao, S. Ritter

Not published at VTT

Paul Scherrer Institute (PSI)

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

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Abstract

The fracture behaviour of low-alloy reactor pressure vessel (RPV) steels with different microstructures, chemical compositions and mechanical properties in simulated light water reactor environments was evaluated by elastic plastic fracture mechanics tests. Moderate but clear environmental reduction of fracture initiation resistance occurred in RPV steels with high yield stress, high dynamic strain aging (DSA), environmentallyassisted cracking (EAC) and temper embrittlement (TE) susceptibilities. Failure occurred dominantly by stable ductile transgranular tearing with micro-void coalescence in both air and high-temperature water environments. Additional and varying amounts (a few %) of secondary cracking, macro-voids, quasi-cleavage and intergranular cracking were observed in hightemperature water environments. The environmental reduction of fracture resistance is due to hydrogen and the main reason for the moderate degradation effects is the low hydrogen availability in high-temperature water.

Original language	English
Title of host publication	19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
Publisher	American Nuclear Society (ANS)
Pages	934-948
Number of pages	15
Edition	cd-rom
ISBN (Electronic)	978-0-89448-765-1
Publication status	Published - 2019
MoE publication type	A4 Article in a conference publication
Event	19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States Duration: 18 Aug 2019 → 22 Aug 2019

Conference

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

Keywords

Dynamic Strain Aging
Environmentally-Assisted Cracking
Fracture Resistance
Hydrogen Embrittlement
Low Alloy Steel
Reactor Pressure Vessel
Temper Embrittlement

Cite this

Que, Z., Seifert, H.-P., Spätig, P., Zhang, A., Holzer, J., Rao, G. S., & Ritter, S. (2019). Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels. In 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (cd-rom ed., pp. 934-948). American Nuclear Society (ANS).

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title = "Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels",

abstract = "The fracture behaviour of low-alloy reactor pressure vessel (RPV) steels with different microstructures, chemical compositions and mechanical properties in simulated light water reactor environments was evaluated by elastic plastic fracture mechanics tests. Moderate but clear environmental reduction of fracture initiation resistance occurred in RPV steels with high yield stress, high dynamic strain aging (DSA), environmentallyassisted cracking (EAC) and temper embrittlement (TE) susceptibilities. Failure occurred dominantly by stable ductile transgranular tearing with micro-void coalescence in both air and high-temperature water environments. Additional and varying amounts (a few %) of secondary cracking, macro-voids, quasi-cleavage and intergranular cracking were observed in hightemperature water environments. The environmental reduction of fracture resistance is due to hydrogen and the main reason for the moderate degradation effects is the low hydrogen availability in high-temperature water.",

keywords = "Dynamic Strain Aging, Environmentally-Assisted Cracking, Fracture Resistance, Hydrogen Embrittlement, Low Alloy Steel, Reactor Pressure Vessel, Temper Embrittlement",

author = "Zaiqing Que and Hans-Peter Seifert and Philippe Sp{\"a}tig and A. Zhang and J. Holzer and Rao, {G. S.} and S. Ritter",

year = "2019",

language = "English",

pages = "934--948",

booktitle = "19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors",

publisher = "American Nuclear Society (ANS)",

address = "United States",

edition = "cd-rom",

note = "19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, ENVDEG 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

}

Que, Z, Seifert, H-P, Spätig, P, Zhang, A, Holzer, J, Rao, GS & Ritter, S 2019, Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels. in 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. cd-rom edn, American Nuclear Society (ANS), pp. 934-948, 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, Boston, United States, 18/08/19.

Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels. / Que, Zaiqing; Seifert, Hans-Peter; Spätig, Philippe et al.
19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. cd-rom. ed. American Nuclear Society (ANS), 2019. p. 934-948.

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

TY - GEN

T1 - Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels

AU - Que, Zaiqing

AU - Seifert, Hans-Peter

AU - Spätig, Philippe

AU - Zhang, A.

AU - Holzer, J.

AU - Rao, G. S.

AU - Ritter, S.

PY - 2019

Y1 - 2019

N2 - The fracture behaviour of low-alloy reactor pressure vessel (RPV) steels with different microstructures, chemical compositions and mechanical properties in simulated light water reactor environments was evaluated by elastic plastic fracture mechanics tests. Moderate but clear environmental reduction of fracture initiation resistance occurred in RPV steels with high yield stress, high dynamic strain aging (DSA), environmentallyassisted cracking (EAC) and temper embrittlement (TE) susceptibilities. Failure occurred dominantly by stable ductile transgranular tearing with micro-void coalescence in both air and high-temperature water environments. Additional and varying amounts (a few %) of secondary cracking, macro-voids, quasi-cleavage and intergranular cracking were observed in hightemperature water environments. The environmental reduction of fracture resistance is due to hydrogen and the main reason for the moderate degradation effects is the low hydrogen availability in high-temperature water.

AB - The fracture behaviour of low-alloy reactor pressure vessel (RPV) steels with different microstructures, chemical compositions and mechanical properties in simulated light water reactor environments was evaluated by elastic plastic fracture mechanics tests. Moderate but clear environmental reduction of fracture initiation resistance occurred in RPV steels with high yield stress, high dynamic strain aging (DSA), environmentallyassisted cracking (EAC) and temper embrittlement (TE) susceptibilities. Failure occurred dominantly by stable ductile transgranular tearing with micro-void coalescence in both air and high-temperature water environments. Additional and varying amounts (a few %) of secondary cracking, macro-voids, quasi-cleavage and intergranular cracking were observed in hightemperature water environments. The environmental reduction of fracture resistance is due to hydrogen and the main reason for the moderate degradation effects is the low hydrogen availability in high-temperature water.

KW - Dynamic Strain Aging

KW - Environmentally-Assisted Cracking

KW - Fracture Resistance

KW - Hydrogen Embrittlement

KW - Low Alloy Steel

KW - Reactor Pressure Vessel

KW - Temper Embrittlement

UR - http://www.scopus.com/inward/record.url?scp=85080094834&partnerID=8YFLogxK

M3 - Conference article in proceedings

SP - 934

EP - 948

BT - 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors

PB - American Nuclear Society (ANS)

T2 - 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019

Y2 - 18 August 2019 through 22 August 2019

ER -

Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels

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Keywords

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