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

Abstract

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 is 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.

Authors:
;  [1]
  1. Oak Ridge National Lab., TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
OSTI Identifier:
543208
Report Number(s):
DOE/ER-0313/22
ON: DE97008797; TRN: 97:020248
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Aug 1997; Related Information: Is Part Of Fusion materials semiannual progress report for period ending June 30, 1997; PB: 358 p.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; 36 MATERIALS SCIENCE; THERMONUCLEAR REACTOR MATERIALS; PHYSICAL RADIATION EFFECTS; FERRITIC STEELS; DUCTILE-BRITTLE TRANSITIONS; DAMAGING NEUTRON FLUENCE; CHROMIUM BASE ALLOYS; PROGRESS REPORT; TEMPERATURE DEPENDENCE

Citation Formats

Klueh, R.L., and Alexander, D.J. Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels. United States: N. p., 1997. Web. doi:10.2172/543208.
Klueh, R.L., & Alexander, D.J. Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels. United States. doi:10.2172/543208.
Klueh, R.L., and Alexander, D.J. Fri . "Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels". United States. doi:10.2172/543208. https://www.osti.gov/servlets/purl/543208.
@article{osti_543208,
title = {Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels},
author = {Klueh, R.L. and Alexander, D.J.},
abstractNote = {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 is 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.},
doi = {10.2172/543208},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Aug 01 00:00:00 EDT 1997},
month = {Fri Aug 01 00:00:00 EDT 1997}
}

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