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Void swelling in the molybdenum alloy TZM irradiated to high fluence

Conference ·
OSTI ID:6256664

Microstructural development and density change measurements are reported for TZM, a commercial molybdenum base alloy, following fast neutron irradiation in EBR-II to high fluence over the temperature range 400 to 650/sup 0/C. Uniformly distributed voids arrayed in a lattice and constituting 3% swelling were observed following irradiation at 650/sup 0/C to 14.7 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) (53 dpa). Nonuniformly distributed rafts of voids in lattice arrays were observed following irradiation at 540/sup 0/C to 13.6 x 10/sup 22/ n/cm/sup 2/. Void swelling was not resolved following irradiation at 425/sup 0/C to 12.2 x 10/sup 22/ n/cm/sup 2/. Void swelling measurements corroborated density change results which showed peak void swelling behavior saturating at 590/sup 0/C. Two mechanisms for the behavior observed are considered; the first is based on an apparent maximum void size of 10 nm which leads to void rafting and eventually to void swelling saturation. Saturation is predicted only after 10/sup 24/ n/cm/sup 2/ (360 dpa) with 20% swelling possible. The second mechanism considers the effect of a developing void lattice on dislocation dynamics. In either case, at goal fluence for a fusion reactor first wall, only 4% swelling is anticipated which would not represent a design limitation.

Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
AC14-76FF02170
OSTI ID:
6256664
Report Number(s):
HEDL-SA-2336-FP; CONF-810831-41; ON: DE81029802
Country of Publication:
United States
Language:
English