Irradiation Creep in the Dounreay Fast Reactor

Irradiation-Induced Creep in Austenitic Stainless Steel.

“…Furthermore, ~se of an effective strain per unit effective stress should provide correlation between the tests in pure tension and torsion. The effettive strain per unit effective stress is defined( 9 ) as (fa ~ y/3T = E/a (2) where (/~is the effective strain per unit effective stress, …”

“…Comparison of the constant load creep curves using the state-of-stress adjustment of Equation (2) results in approximately six times more creep in uniaxial tension than in torsion. ·Comparison of the same data, but using the state-ofstress adjustment of Equation (4) is shown in Figure 3 .…”

Irradiation Creep in Materials

“…There is some evidence that the creep rate of cold-worked (CW) materials is larger than the one of solution annealed (SA) materials, at least at low dose (Mosedale, et al, 1972) (Straalsund, 1977) (Walters, et al, 1977). However, in the secondary creep regime there is often no significant difference between CW and SA materials, especially for austenitic stainless steels (Mosedale, et al, 1977) . Concerning zirconium alloys, there is a low dependency to dislocation density, the creep rate being higher when the dislocation density increase.…”

Thirty years of fuels and materials information from EBR-II

“…When EBR-II was designed, irradiation phenomena that changed the mechanical properties of steel were largely unknown because no fast reactors had operated prior to EBR-II for a long enough period to notice these changes. Void swelling and irradiation enhanced creep along with irradiation induced embrittlement appeared as problems that were accommodated as operation of EBR-II continued [8,9]. Irradiation induced property changes were, of course, issues only in the primary system of EBR-II.…”