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Heat treatment effects on toughness of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated at 365°C

Conference · · Journal of Nuclear Materials
 [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The 9Cr-1MoVNb and 12Cr-1MoVW steels were austenitized at 1040 and 1100°C to produce different prior austenite grain sizes, after which they were given different tempering treatments (1 h at 760 or 2.5 h at 780°C). Subsize Charpy impact specimens from these materials were irradiated at 365°C up to 5 dpa. For 9Cr-1MoVNb steel in the unirradiated condition, the smaller the prior austenite grain size and the higher the tempering temperature, the lower the ductile-brittle transition temperature (DBTT). Regardless of the DBTT in the unirradiated condition, however, the DBTT shift for 9Cr-1MoVNb steel due to irradiation was the same for all heat treatments. This means heat treatment can be used to ensure a lower DBTT before and after irradiation. The 12Cr-1MoVW steel showed little effect of heat treatment on DBTT in the unirradiated condition, and the shift in DBTT was relatively constant. Thus, it appears that heat treatment cannot be used to reduce the effect of irradiation on DBTT for this steel.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
10115547
Report Number(s):
CONF-911111--32; ON: DE92006592
Resource Type:
Conference paper/presentation
Conference Information:
Journal Name: Journal of Nuclear Materials Journal Issue: B
Country of Publication:
United States
Language:
English

References (6)

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Effects of irradiation on ferritic alloys and implications for fusion reactor applications journal July 1987
Effect of nickel content of 9Cr-1MoVNb and 12Cr-1MoVW steels on the aging and irradiation response of impact properties journal August 1987
Impact behavior of 9-Cr and 12-Cr ferritic steels after low-temperature irradiation journal July 1988
Impact behavior of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated in HFIR journal March 1991