Published October 15, 2006 | Version v1
Journal article

Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study

  • 1. Oak Ridge National Laboratory, P.O. Box 2008, MS 6151, Oak Ridge, Tennessee 37831-6151 (United States)
  • 2. Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Tokai, Ibaraki 319-1195 (Japan)

Description

Tensile and Charpy specimens of 9Cr-1MoVNb (modified 9Cr-1Mo) and 12Cr-1MoVW (Sandvik HT9) steels and these steels doped with 2% Ni were irradiated at 300 and 400 deg. C in the High Flux Isotope Reactor (HFIR) up to ∼12 dpa and at 393 deg. C in the Fast Flux Test Facility (FFTF) to ∼15 dpa. In HFIR, a mixed-spectrum reactor (n, α) reactions of thermal neutrons with 58Ni produce helium in the steels. Little helium is produced during irradiation in FFTF. After HFIR irradiation, the yield stress of all steels increased, with the largest increases occurring for nickel-doped steels. The ductile-brittle transition temperature (DBTT) increased up to two times and 1.7 times more in steels with 2% Ni than in those without the nickel addition after HFIR irradiation at 300 and 400 deg. C, respectively. Much smaller differences occurred between these steels after irradiation in FFTF. The DBTT increases for steels with 2% Ni after HFIR irradiation were 2-4 times greater than after FFTF irradiation. Results indicated there was hardening due to helium in addition to hardening by displacement damage and irradiation-induced precipitation

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2006.05.048;
PII
S0022-3115(06)00340-0;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
357
Journal Issue
1-3
Journal Page Range
p. 156-168
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

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