Defect development in neutron irradiated type 316 stainless steel

Void-Precipitate Association During Neutron Irradiation of Austenitic Stainless Steel

“…Relative to observations on many other heats of SA 315 irradiated in EBR-II [9,10,[31][32][33][34][35], this 00 heat has far fewer total voids, but a larger fraction of precipitate associated voids. The other heats of steel have, in general, many more loops and higher dislocation concentrations.…”

“…Large voids directly associated with precipitate phase particles have been a prominent feature of the microstructure of neutron irradiated stainless steels since the discovery of voids nearly 20 years ago [1], However, that association did not receive much experimental or theoretical attention until recently [2][3][4][5][6][7][8], Some investigators did single out the phenomenon [9,10] and proposed [9,11] possible mechanisms that would enhance void formation and growth at a precipitate/matrix interface.…”

“…Brager and Straalsund [9] suggested that helium and vacancies preferentially accumulate to particular interfaces to assist void evolution.…”

“…From 1972From -1978, the discovery of many irradiation induced [9,17,13] and/or nickel and silicon rich phases [19,20], suggested that precipitation under irradiation may be quite different from that occurring under thermal aging.…”

A Microstructural Interpretation of the Fluence and Temperature Dependence of the Mechanical Properties of Irradiated AISI 316

“…(!Nd)max = 48,000 ¢to.2a ( 19) The data ( 22 ) and caltulated lines for several fluences are shown in Figure 7.…”