Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments

S. Teysseyre; J. H. Jackson; P. L. Andresen; P. Chou; B. Carter

doi:10.1007/978-3-319-68454-3_75

Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments

S. Teysseyre
, J. H. Jackson
, P. L. Andresen
, P. Chou
, B. Carter

Nuclear Reactor Technology

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 10²⁰ n/cm² (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Publisher	Springer International Publishing
Pages	2243-2253
Number of pages	11
ISBN (Print)	9783319684536
DOIs	https://doi.org/10.1007/978-3-319-68454-3_75 https://doi.org/10.1007/978-3-030-04639-2_151
State	Published - Oct 7 2017
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: Aug 18 2019 → Aug 22 2019

Publication series

Name	Minerals, Metals and Materials Series
Volume	Part F11
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Conference

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

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Teysseyre, S., Jackson, J. H., Andresen, P. L., Chou, P., & Carter, B. (2017). Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 2243-2253). (Minerals, Metals and Materials Series; Vol. Part F11). Springer International Publishing. https://doi.org/10.1007/978-3-319-68454-3_75, https://doi.org/10.1007/978-3-030-04639-2_151

Teysseyre, S. ; Jackson, J. H. ; Andresen, P. L. et al. / Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing, 2017. pp. 2243-2253 (Minerals, Metals and Materials Series).

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title = "Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments",

abstract = "The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 1020 n/cm2 (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.",

author = "S. Teysseyre and Jackson, \{J. H.\} and Andresen, \{P. L.\} and P. Chou and B. Carter",

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",

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language = "English",

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series = "Minerals, Metals and Materials Series",

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Teysseyre, S, Jackson, JH, Andresen, PL, Chou, P & Carter, B 2017, Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments. in Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Minerals, Metals and Materials Series, vol. Part F11, Springer International Publishing, pp. 2243-2253, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 08/18/19. https://doi.org/10.1007/978-3-319-68454-3_75, https://doi.org/10.1007/978-3-030-04639-2_151

Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments. / Teysseyre, S.; Jackson, J. H.; Andresen, P. L. et al.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing, 2017. p. 2243-2253 (Minerals, Metals and Materials Series; Vol. Part F11).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments

AU - Teysseyre, S.

AU - Jackson, J. H.

AU - Andresen, P. L.

AU - Chou, P.

AU - Carter, B.

PY - 2017/10/7

Y1 - 2017/10/7

N2 - The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 1020 n/cm2 (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.

AB - The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 1020 n/cm2 (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.

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AN - SCOPUS:85064066026

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T3 - Minerals, Metals and Materials Series

SP - 2243

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

PB - Springer International Publishing

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Teysseyre S, Jackson JH, Andresen PL, Chou P, Carter B. Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing. 2017. p. 2243-2253. (Minerals, Metals and Materials Series). doi: 10.1007/978-3-319-68454-3_75, 10.1007/978-3-030-04639-2_151

Irradiation assisted stress corrosion cracking susceptibility of alloy X-750 exposed to BWR environments

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