Published June 1990 | Version v1
Report Restricted

Swelling of neutron irradiated vanadium alloys

  • 1. Argonne National Lab., IL (USA)
  • 2. Pacific Northwest Lab., Richland, WA (USA)

Description

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 CCl4. 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 <0.1% swelling per dpa

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A02/MF A01 as DE90015294; OSTI; INIS; US Govt. Printing Office Dep.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
PNL-SA--17175

Optional Information

Contract/Grant/Project number
Contract AC06-76RL01830; W-31109-ENG-38