Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels

Y. Nishiyama; K. Onizawa; M. Suzuki; J. W. Anderegg; Y. Nagai; T. Toyama; M. Hasegawa; J. Kameda

doi:10.1016/j.actamat.2008.05.026

Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels

Y. Nishiyama, K. Onizawa, M. Suzuki, J. W. Anderegg, Y. Nagai, T. Toyama, M. Hasegawa, J. Kameda

Research output: Contribution to journal › Article › peer-review

53 Citations (Scopus)

Abstract

The effects of intergranular P segregation and hardening on the ductile-to-brittle transition temperature (DBTT) in several neutron-irradiated reactor pressure vessel steels with different bulk contents of P and Cu have been investigated using a scanning Auger microbe, a local electrode atom probe and positron annihilation spectroscopy. Increasing the neutron fluence at 563 K promotes intergranular P segregation, particularly in steels with high levels of P. The content of P (<570 ppm) more significantly affects irradiation-hardening than that of Cu (<0.17 wt.%) due to distinct formation of P-rich precipitates arising from the stabilization of vacancies. Analyzing the correlations between P segregation, hardening, fraction of intergranular fracture and DBTT, it is found neutron irradiation mitigates the embrittling effect of segregated P, and therefore the hardening more strongly affects the DBTT shift than the P segregation, with the exception of highly P-doped steel irradiated to high neutron fluence.

Original language	English
Pages (from-to)	4510-4521
Number of pages	12
Journal	Acta Materialia
Volume	56
Issue number	16
DOIs	https://doi.org/10.1016/j.actamat.2008.05.026
Publication status	Published - 2008 Oct

Keywords

Grain-boundary segregation
Hardening
Irradiation embrittlement
Precipitate
Reactor pressure vessel steels

ASJC Scopus subject areas

Electronic, Optical and Magnetic Materials
Ceramics and Composites
Polymers and Plastics
Metals and Alloys

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10.1016/j.actamat.2008.05.026

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Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels. / Nishiyama, Y.; Onizawa, K.; Suzuki, M.; Anderegg, J. W.; Nagai, Y.; Toyama, T.; Hasegawa, M.; Kameda, J.

In: Acta Materialia, Vol. 56, No. 16, 10.2008, p. 4510-4521.

Research output: Contribution to journal › Article › peer-review

@article{b873a759dc46468386f0d6578b1ef357,

title = "Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels",

abstract = "The effects of intergranular P segregation and hardening on the ductile-to-brittle transition temperature (DBTT) in several neutron-irradiated reactor pressure vessel steels with different bulk contents of P and Cu have been investigated using a scanning Auger microbe, a local electrode atom probe and positron annihilation spectroscopy. Increasing the neutron fluence at 563 K promotes intergranular P segregation, particularly in steels with high levels of P. The content of P (<570 ppm) more significantly affects irradiation-hardening than that of Cu (<0.17 wt.%) due to distinct formation of P-rich precipitates arising from the stabilization of vacancies. Analyzing the correlations between P segregation, hardening, fraction of intergranular fracture and DBTT, it is found neutron irradiation mitigates the embrittling effect of segregated P, and therefore the hardening more strongly affects the DBTT shift than the P segregation, with the exception of highly P-doped steel irradiated to high neutron fluence.",

keywords = "Grain-boundary segregation, Hardening, Irradiation embrittlement, Precipitate, Reactor pressure vessel steels",

author = "Y. Nishiyama and K. Onizawa and M. Suzuki and Anderegg, {J. W.} and Y. Nagai and T. Toyama and M. Hasegawa and J. Kameda",

note = "Funding Information: A part of this work was carried out under a contract between the Ministry of Economy, Trade and Industry of Japan and JAEA. Ames Laboratory is operated for the US Department of Energy, Iowa State University under Contract No. W-7405-ENG-82. This study was performed under the Work for Other program approved by the Office of Basic Energy Sciences, Division of Materials Sciences while one of the authors (J.K.) was affiliated with the Ames Laboratory. The authors would like to thank M. Yamaguchi for valuable discussions, and A.H. Swanson, Z. Zhang and J. Sekino for experimental assistance. Copyright: Copyright 2008 Elsevier B.V., All rights reserved.",

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AU - Nishiyama, Y.

AU - Onizawa, K.

AU - Suzuki, M.

AU - Anderegg, J. W.

AU - Nagai, Y.

AU - Toyama, T.

AU - Hasegawa, M.

AU - Kameda, J.

N1 - Funding Information: A part of this work was carried out under a contract between the Ministry of Economy, Trade and Industry of Japan and JAEA. Ames Laboratory is operated for the US Department of Energy, Iowa State University under Contract No. W-7405-ENG-82. This study was performed under the Work for Other program approved by the Office of Basic Energy Sciences, Division of Materials Sciences while one of the authors (J.K.) was affiliated with the Ames Laboratory. The authors would like to thank M. Yamaguchi for valuable discussions, and A.H. Swanson, Z. Zhang and J. Sekino for experimental assistance. Copyright: Copyright 2008 Elsevier B.V., All rights reserved.

PY - 2008/10

Y1 - 2008/10

N2 - The effects of intergranular P segregation and hardening on the ductile-to-brittle transition temperature (DBTT) in several neutron-irradiated reactor pressure vessel steels with different bulk contents of P and Cu have been investigated using a scanning Auger microbe, a local electrode atom probe and positron annihilation spectroscopy. Increasing the neutron fluence at 563 K promotes intergranular P segregation, particularly in steels with high levels of P. The content of P (<570 ppm) more significantly affects irradiation-hardening than that of Cu (<0.17 wt.%) due to distinct formation of P-rich precipitates arising from the stabilization of vacancies. Analyzing the correlations between P segregation, hardening, fraction of intergranular fracture and DBTT, it is found neutron irradiation mitigates the embrittling effect of segregated P, and therefore the hardening more strongly affects the DBTT shift than the P segregation, with the exception of highly P-doped steel irradiated to high neutron fluence.

AB - The effects of intergranular P segregation and hardening on the ductile-to-brittle transition temperature (DBTT) in several neutron-irradiated reactor pressure vessel steels with different bulk contents of P and Cu have been investigated using a scanning Auger microbe, a local electrode atom probe and positron annihilation spectroscopy. Increasing the neutron fluence at 563 K promotes intergranular P segregation, particularly in steels with high levels of P. The content of P (<570 ppm) more significantly affects irradiation-hardening than that of Cu (<0.17 wt.%) due to distinct formation of P-rich precipitates arising from the stabilization of vacancies. Analyzing the correlations between P segregation, hardening, fraction of intergranular fracture and DBTT, it is found neutron irradiation mitigates the embrittling effect of segregated P, and therefore the hardening more strongly affects the DBTT shift than the P segregation, with the exception of highly P-doped steel irradiated to high neutron fluence.

KW - Grain-boundary segregation

KW - Hardening

KW - Irradiation embrittlement

KW - Precipitate

KW - Reactor pressure vessel steels

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Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels

Abstract

Keywords

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