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Title: Investigation of the development of irradiation-induced precipitates in VVER-440 type reactor pressure vessel steels and weld metals after irradiation and annealing

Conference ·
OSTI ID:679495
; ;  [1];  [2]
  1. Inst. for Safety Research, Dresden (Germany). Neutron Embrittlement Div.
  2. TU Dresden (Germany). Positron Group

The development of irradiation-induced precipitates in VVER-440 type reactor pressure vessel steels 15Kh2MFA and weld metals SV-10KhMFT during irradiation and post-irradiation annealing is studied by small angle neutron and X-ray scattering. The kinetic conditions for the precipitation of particles, which already exist in the unirradiated state, seem to be improved at temperatures of about 270 C due to the irradiation. The size distribution of the irradiation-induced precipitates depends on the copper content and differs between weld and base metal. A strong correlation between the formation of irradiation-induced precipitates and the irradiation hardening is found. The hardness nearly linearly depends on the number of these precipitates.

OSTI ID:
679495
Report Number(s):
CONF-960643-; TRN: 99:009428
Resource Relation:
Conference: 18. symposium on effects of radiation on materials, Hyannis, MA (United States), 25-27 Jun 1996; Other Information: PBD: 1999; Related Information: Is Part Of Effects of radiation on materials: 18. international symposium; Nanstad, R.K. [ed.] [Oak Ridge National Lab., TN (United States)]; Hamilton, M.L.; Garner, F.A. [eds.] [Pacific Northwest National Lab., Richland, WA (United States)]; Kumar, A.S. [ed.] [Univ. of Missouri, Rolla, MO (United States)]; PB: 1261 p.; ASTM special technical publication 1325
Country of Publication:
United States
Language:
English