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P . J . Maziasz, F. W. W i f f e n and E. E Bloom, " S w e l l i n g and M i c r o s t r u c t u r a l Changes i n Type 316 S t a i n l e s s S t e e l I r r a d i a t e d Under Simulated CTR Conditions," R a d i a t i o n E f f e c t s and T r i t i u m Technology f o r F u s i o n Reactors, J . S. Watson and F. W. , CONF-750989, March 1976. 11. P . 3 . Maziasz, "Helium T r a p p i n g a t T i R i c h MC P a r t i c l e s i n T i M o d i f i e d A u s t e n t i c S t a i n l e s s Steel," A I M E Symposium on Phase S t a b i l i t y D u r i n g I r r a d i a t i o n , J .

18 The precipitate contribution is limited by the amount of precipitate material available. Voids can increase the Auys until the irradiation conditions terminate void nucleation and growth. Since the void microstructure eventually dominate the hardenin in stainless steel, it is of value to study this source further. ,% looked at microstructure evolution in stainless steel irradiated with dual ions (Ni and Helium) at 600°C. The helium to dpa ratio fhpa/dpa) used to simulated a fusion environment varied between 5 : l to 50:l.

Hater. I 103 & 104, p. 1075, 1981. 20 FIGURE 2 . Examples o f Microstructures Observed in AISI 216 Irradiated at 427 and 593°C. Figures 2 g and 2 h provide a comparison with 20% cold-worked AISI 316 specimens irradiated under identical conditions. 34% at 593°C. 1 MeV) FIGURE 3 . Swelling in AIS1 216 Irradiated with the 6109 Test Plotted as a Function of Fluence. No strong dependence on irradiation temperature is observed. D. 5. R. M. Boothby, D. R. Harries and T. M. Williams, J. Nucl. 6. J. F. Bates and R.

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Damage [radiation] Analysis, Fund. Studies [qtrly rpt Jan-Mar 1984]

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