The compositional dependence of irradiation creep of austenitic alloys irradiated in PFR at 420{degrees}C
- Pacific Northwest National Lab., Richland, WA (United States)
- AEA Technology, Dounreay (United Kingdom); and others
Irradiation creep data are expensive and often difficult to obtain, especially when compared to swelling data. This requires that maximum use be made of available data sources in order to elucidate the parametric dependencies of irradiation creep for application to new alloys and to new environments such as those of proposed fusion environments. One previously untapped source of creep data is that of a joint U.S./U.K. experiment conducted in the Prototype Fast Reactor (PFR) in Dounreay, Scotland. In this experiment, five austenitic steels were irradiated in a variety of starting conditions. In particular, these steels spanned a large range (15-40%) of nickel contents, and contained strong variations in Mo, Ti, Al, and Nb. Some alloys were solution-strengthened and some were precipitation-strengthened. Several were cold-worked. These previously unanalyzed data show that at 420{degrees}C all austenitic steels have a creep compliance that is roughly independent of the composition of the steel at 2{+-}1 x 10{sup {minus}6}MPa{sup {minus}1} dpa{sup {minus}1}. The variation within this range may arise from the inability to completely separate the non-creep strains arising from precipitation reactions and the stress-enhancement of swelling. Each of these can be very sensitive to the composition and starting treatment of a steel.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OSTI ID:
- 543297
- Report Number(s):
- DOE/ER-0313/21; ON: DE97008798; TRN: 97:020339
- Resource Relation:
- Other Information: PBD: Apr 1997; Related Information: Is Part Of Fusion materials semiannual progress report for the period ending December 31, 1996; PB: 296 p.
- Country of Publication:
- United States
- Language:
- English
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