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Swelling of neutron irradiated vanadium alloys

Technical Report ·
DOI:https://doi.org/10.2172/6730342· OSTI ID:6730342
;  [1];  [2]
  1. Argonne National Lab., IL (USA)
  2. Pacific Northwest Lab., Richland, WA (USA)
The swelling of V-10.0Cr-0.1Al, 1Cr-0.3Al, V-3.1Ti-0.3Sl, V-4.9Ti, V-14.4Ti, V-17.7Ti, V-20.0Ti, V-14.4Cr-0.3Ti-0.3Al, V-14.1Cr-1.0Ti-0.3Al, V-13.7Cr-4.8Ti, V-9.0Cr-3.3Fe-1.2Zr (Vanstar-7), V-14.5Ti-7.2Cr, V-8.6W, V-4.0Mo, and V-12.3 Ni alloys and unalloyed V was determined after neutron irradiation at 420{degree}C and 600{degree}C to irradiation damage levels ranging from 17 to 77 dpa in the FFTF-MOTA reactor facility. The swelling of these alloys was obtained from a determination of the density for the unirradiated and irradiated alloys on immersion in CCl{sub 4}. The swelling of unalloyed V at 600{degree}C was substantially increased by the addition of Cr. The addition of either Ni, W, or Mo to V had relatively minor effect on the swelling of V. The swelling of the V-Cr-Ti alloys was strongly dependent on the Ti concentration. The swelling of the V-3.1Ti-0.3Si and V-14.4Ti alloys at 600{degree}C was greater than that exhibited by the other binary V-Ti alloys. The Vanstar-7 alloy underwent larger swelling that the V-Ti and V-Cr-Ti alloys. For the binary V-Ti alloys and the ternary V-Cr-Tl alloys, the dependence of swelling on the amount of irradiation damage was {lt}0.1% swelling per dpa.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Organization:
DOE/NE
DOE Contract Number:
AC06-76RL01830; W-31109-ENG-38
OSTI ID:
6730342
Report Number(s):
PNL-SA-17175; ON: DE90015294
Country of Publication:
United States
Language:
English