Published December 1, 2006 | Version v1
Journal article

Microstructure and mechanical properties of austenitic stainless steel 12X18H9T after neutron irradiation in the pressure vessel of BR-10 fast reactor at very low dose rates

  • 1. Institute of Physics and Power Engineering, Bondarenko Square 1, Obninsk, Kaluga Region 249033 (Russian Federation)
  • 2. Pacific Northwest National Laboratory, Materials Resources Department, 902 Battelle Boulevard, MS P8-15, Richland, WA 99354 (United States)

Description

Results are presented for void swelling, microstructure and mechanical properties of Russian 12X18H9T (0.12C-18Cr-9Ni-Ti) austenitic stainless steel irradiated as a pressure vessel structural material of the BR-10 fast reactor at ∼350 deg. C to only 0.64 dpa, produced by many years of exposure at the very low displacement rate of only 1.9 x 10-9 dpa/s. In agreement with a number of other recent studies it appears that lower dpa rates have a pronounced effect on the microstructure and resultant mechanical properties. In general, lower dpa rates lead to the onset of swelling at much lower doses compared to comparable irradiations conducted at higher dpa rates

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2006.07.015;
PII
S0022-3115(06)00414-4;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
359
Journal Issue
1-2
Journal Page Range
p. 41-49
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.