Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic/martensitic steel for a high power spallation neutron source

E. H. Lee; J. D. Hunn; G. R. Rao; R. L. Klueh; L. K. Mansur

doi:10.1016/S0022-3115(98)00722-3

Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic/martensitic steel for a high power spallation neutron source

E. H. Lee, J. D. Hunn, G. R. Rao, R. L. Klueh, L. K. Mansur

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Abstract

To simulate radiation damage under a future Spallation Neutron Source (SNS) environment, irradiation experiments were conducted on a candidate 9Cr-2WVTa ferritic/martensitic steel using the Triple Ion Facility (TIF) at ORNL. Irradiation was conducted in single, dual and triple ion beam modes using 3.5 MeV Fe⁺⁺, 360 keV He⁺, and 180 keV H⁺ at 80°C, 200°C and 350°C. These irradiations produced various defects comprising black dots, dislocation loops, line dislocations, and gas bubbles, which led to hardening. The largest increase in hardness, over 63%, was observed after 50 dpa for triple beam irradiation conditions, revealing that both He and H are augmenting the hardening. Hardness increased less than 30% after 30 dpa at 200°C by triple beams, compatible with neutron irradiation data from previous work which showed about a 30% increase in yield strength after 27.2 dpa at 365°C. However, the very large concentrations of gas bubbles in the matrix and on lath and grain boundaries after these simulated SNS irradiations make predictions of fracture behavior from fission reactor irradiations to spallation target conditions inadvisable.

Original language	English
Pages (from-to)	385-390
Number of pages	6
Journal	Journal of Nuclear Materials
Volume	271-272
DOIs	https://doi.org/10.1016/S0022-3115(98)00722-3
State	Published - May 1999
Event	Proceedings of the 1997 8th International Conference on Fusion Reactor Materials (ICFRM-8), Part C - Sendai, Jpn Duration: Oct 26 1997 → Oct 31 1997

Funding

This research was sponsored by the Division of Materials Sciences, US Department of Energy, under contract No. DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation. The authors would like to thank Dr M.B. Lewis and Mr S.W. Cook for assisting accelerator irradiation, and Drs K. Farrell and R.E. Stoller for technical review of the manuscript.

Funders	Funder number
Division of Materials Sciences
Lockheed Martin Energy Research Corporation
U.S. Department of Energy	DE-AC05-96OR22464

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title = "Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic/martensitic steel for a high power spallation neutron source",

abstract = "To simulate radiation damage under a future Spallation Neutron Source (SNS) environment, irradiation experiments were conducted on a candidate 9Cr-2WVTa ferritic/martensitic steel using the Triple Ion Facility (TIF) at ORNL. Irradiation was conducted in single, dual and triple ion beam modes using 3.5 MeV Fe++, 360 keV He+, and 180 keV H+ at 80°C, 200°C and 350°C. These irradiations produced various defects comprising black dots, dislocation loops, line dislocations, and gas bubbles, which led to hardening. The largest increase in hardness, over 63%, was observed after 50 dpa for triple beam irradiation conditions, revealing that both He and H are augmenting the hardening. Hardness increased less than 30% after 30 dpa at 200°C by triple beams, compatible with neutron irradiation data from previous work which showed about a 30% increase in yield strength after 27.2 dpa at 365°C. However, the very large concentrations of gas bubbles in the matrix and on lath and grain boundaries after these simulated SNS irradiations make predictions of fracture behavior from fission reactor irradiations to spallation target conditions inadvisable.",

author = "Lee, {E. H.} and Hunn, {J. D.} and Rao, {G. R.} and Klueh, {R. L.} and Mansur, {L. K.}",

year = "1999",

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doi = "10.1016/S0022-3115(98)00722-3",

language = "English",

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T1 - Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic/martensitic steel for a high power spallation neutron source

AU - Lee, E. H.

AU - Hunn, J. D.

AU - Rao, G. R.

AU - Klueh, R. L.

AU - Mansur, L. K.

PY - 1999/5

Y1 - 1999/5

N2 - To simulate radiation damage under a future Spallation Neutron Source (SNS) environment, irradiation experiments were conducted on a candidate 9Cr-2WVTa ferritic/martensitic steel using the Triple Ion Facility (TIF) at ORNL. Irradiation was conducted in single, dual and triple ion beam modes using 3.5 MeV Fe++, 360 keV He+, and 180 keV H+ at 80°C, 200°C and 350°C. These irradiations produced various defects comprising black dots, dislocation loops, line dislocations, and gas bubbles, which led to hardening. The largest increase in hardness, over 63%, was observed after 50 dpa for triple beam irradiation conditions, revealing that both He and H are augmenting the hardening. Hardness increased less than 30% after 30 dpa at 200°C by triple beams, compatible with neutron irradiation data from previous work which showed about a 30% increase in yield strength after 27.2 dpa at 365°C. However, the very large concentrations of gas bubbles in the matrix and on lath and grain boundaries after these simulated SNS irradiations make predictions of fracture behavior from fission reactor irradiations to spallation target conditions inadvisable.

AB - To simulate radiation damage under a future Spallation Neutron Source (SNS) environment, irradiation experiments were conducted on a candidate 9Cr-2WVTa ferritic/martensitic steel using the Triple Ion Facility (TIF) at ORNL. Irradiation was conducted in single, dual and triple ion beam modes using 3.5 MeV Fe++, 360 keV He+, and 180 keV H+ at 80°C, 200°C and 350°C. These irradiations produced various defects comprising black dots, dislocation loops, line dislocations, and gas bubbles, which led to hardening. The largest increase in hardness, over 63%, was observed after 50 dpa for triple beam irradiation conditions, revealing that both He and H are augmenting the hardening. Hardness increased less than 30% after 30 dpa at 200°C by triple beams, compatible with neutron irradiation data from previous work which showed about a 30% increase in yield strength after 27.2 dpa at 365°C. However, the very large concentrations of gas bubbles in the matrix and on lath and grain boundaries after these simulated SNS irradiations make predictions of fracture behavior from fission reactor irradiations to spallation target conditions inadvisable.

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JO - Journal of Nuclear Materials

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ER -

Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic/martensitic steel for a high power spallation neutron source

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