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Title: Saturation of the DBTT shift of irradiated 12Cr-1MoVW with increasing fluence

Conference ·
OSTI ID:6042929

Ferritic/martensitic steels are considered one of the prime candidate materials for structural applications in fusion reactors. This class of steel provides many advantages including excellent swelling resistance and high thermal conductivity. A reiew of current results on the suitability of ferritic/martensitic steels reveals their corrosion behavior and postirradiation properties are, in general, quite promising. However, a major concern is the existence in these steels of a ductile-to-brittle transition temperature (DBTT), below which the steel has limited ductility and fails in a brittle mode. Although the DBTT, as measured in a Charpy impact test, may be below room temperature in the unirradiated condition, irradiation can increase the DBTT significantly, and the increase depends on the irradiation temperature. Increases in the DBTT of greater than 100/sup 0/C have been measured following irradiation at 400/sup 0/C and below.

Research Organization:
Oak Ridge National Lab., TN (USA); Materials Engineering Associates, Inc., Lanham, MD (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6042929
Report Number(s):
CONF-860421-32; ON: DE86010393
Resource Relation:
Conference: 2. international conference on fusion reactor materials (ICFRM-2), Chicago, IL, USA, 13 Apr 1986; Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English