Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels

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Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants. The major obstacle to their use is embrittlement caused by neutron irradiation. Observations on this irradiation embrittlement will be reviewed. Below 425-450{degrees}C, neutron irradiation hardens the steels. Hardening reduces ductility, but the major effect is an increase in the ductile-brittle transition temperature (DBTT) and a decrease in the upper-shelf energy, as measured by a Charpy impact test. After irradiation, DBTT values can increase to well above room temperature, thus increasing the chances of brittle rather than ductile ... continued below

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13 p.

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Klueh, R.L. & Alexander, D.J. June 1, 1997.

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Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants. The major obstacle to their use is embrittlement caused by neutron irradiation. Observations on this irradiation embrittlement will be reviewed. Below 425-450{degrees}C, neutron irradiation hardens the steels. Hardening reduces ductility, but the major effect is an increase in the ductile-brittle transition temperature (DBTT) and a decrease in the upper-shelf energy, as measured by a Charpy impact test. After irradiation, DBTT values can increase to well above room temperature, thus increasing the chances of brittle rather than ductile fracture. In addition to irradiation hardening, neutrons from the fusion reaction will produce large amounts of helium in the steels used to construct fusion power plant components. Tests to simulate the fusion environment indicate that helium can also affect the toughness. Steels are being developed for fusion applications that have a low DBTT prior to irradiation and then show only a small shift after irradiation. A martensitic 9Cr-2WVTa (nominally Fe-9Cr-2W-0.25V-0.07Ta-0.1C) steel had a much lower DBTT than the conventional 9Cr-1MoVNb steel prior to neutron irradiation and showed a much smaller increase in DBTT after irradiation. 27 refs., 5 figs., 1 tab.

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13 p.

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INIS; OSTI as DE97006317

Medium: P; Size: 13 p.

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  • 126. annual meeting of the Minerals, Metals and Materials Society, Orlando, FL (United States), 9-13 Feb 1997

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  • Other: DE97006317
  • Report No.: CONF-970201--30
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 485950
  • Archival Resource Key: ark:/67531/metadc675659

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  • June 1, 1997

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  • July 25, 2015, 2:21 a.m.

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  • April 7, 2017, 12:48 p.m.

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Klueh, R.L. & Alexander, D.J. Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels, article, June 1, 1997; Tennessee. (digital.library.unt.edu/ark:/67531/metadc675659/: accessed November 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.