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Klueh, R.L.; Alexander, D.J.
Fusion materials semiannual progress report for period ending June 30, 19971997
Fusion materials semiannual progress report for period ending June 30, 19971997
AbstractAbstract
[en] 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
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Oak Ridge National Lab., TN (United States); 358 p; Aug 1997; p. 129; Also available from OSTI as DE97008797; NTIS; US Govt. Printing Office Dep
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Report
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Progress Report
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