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Title: Effects of irradiation on low-activation ferritic alloys

Technical Report ·
DOI:https://doi.org/10.2172/6423769· OSTI ID:6423769

The objective of this work is to provide guidance on the applicability of low activation bainitic and martensitic steels for fusion reactor structural components. A series of low activation ferritic alloys has been designed, fabricated, irradiated in MOTA 1B, and tested and examined following irradiation. The series consists of alloys similar to 2-1/4Cr-1Mo with vanadium substituted for molybdenum, alloys similar to 9Cr-1Mo with tungsten and/or vanadium substituted for molybdenum and alloys similar to HT-9 with tungsten and/or vanadium substituted for molybdenum. The results demonstrate that low activation alloys can be successfully produced in the ferritic alloy class. The 2-1/4Cr-V alloys develop excessive irradiation hardening due to precipitation following irradiation at 420/degree/C and the 2-1/4Cr-V and 9Cr-V/W alloys developed excessive softening due to precipitate coarsening and dislocation recovery following irradiation at 585/degree/C. In comparison, the 12Cr-W-V alloy appears to have excellent properties; ..cap alpha..' precipitation at 420/degree/C in-reactor did not significantly increase strength and reasonable strength was maintained after irradiation at 585/degree/C probably in part due to intermetallic precipitate development. 11 refs., 7 figs., 3 tabs.

Research Organization:
Hanford Engineering Development Lab., Richland, WA (United States)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6423769
Report Number(s):
HEDL-7513; ON: DE89010149
Resource Relation:
Other Information: Paper copy only, copy does not permit microfiche production
Country of Publication:
United States
Language:
English