Published November 1986 | Version v1
Journal article

Postirradiation tensile behavior of nickel-doped ferritic steels

  • 1. Oak Ridge National Lab., TN (USA). Metals and Ceramics Div.

Description

Tensile specimens of normalized-and-tempered 9Cr-1MoVNb, 9Cr-1MoVNb-2Ni, 12Cr-1MoVW, 12Cr-1MoVW-1Ni, and 12Cr-1MoVW-2Ni were irradiated in the Experimental Breeder Reactor (EBR-II) at 390, 450, 500, and 5500C to displacement-damage levels of approximately 16 dpa. The nickel in these steels was added to produce helium during irradiation in a mixed-spectrum reactor. Irradiation of these steels in the fast-spectrum EBR-II, where little helium is formed, helped determine the effect of helium on properties. The nickel-doped steels were stronger prior to irradiation due to a lower tempering temperature. After irradiation, the properties of the steels with and without nickel were similar, indicating that the presence of nickel did not affect the behavior of the steels during irradiation. These fast-reactor results indicate that it is feasible to use the nickel-doped ferritic steels to study helium effects. (orig.)

Additional details

Publishing Information

Journal Title
J. Nucl. Mater.
Journal Volume
141-143
Journal Issue
pt.B
Series
J. Nucl. Mater.
Journal Page Range
960-965
ISSN
0022-3115
CODEN
JNUMA

Conference

Title
2. international conference on fusion reactor materials (ICFRM-2).
Dates
13-17 Apr 1986.
Place
Chicago, IL (USA).

Optional Information

Contract/Grant/Project number
Contract DE-AC05-84OR21400
Notes
Also published as report CONF--860421-25.