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Brager, H.R.; Blackburn, L.D.; Greenslade, D.L.
Hanford Engineering Development Lab., Richland, WA (USA)1983
Hanford Engineering Development Lab., Richland, WA (USA)1983
AbstractAbstract
[en] Annealed specimens of AISI 304 and 316 were irradiated in the EBR-II fast reactor at approx. 4000C over a range of neutron fluxes and energy spectra. Tensile tests show that the hardening of the AISI 304 is sensitive to the displacement rate while the hardening of AISI 316 is not. However, the microstructures of both AISI 304 and 316 are influenced by displacement rate. The increase in yield strength of the specimens is correlated with the contribution of the various microstructural components produced during irradiation. The insensitivity in the hardening of AISI 316 to displacement rate arises because the strengthening contribution from precipitates increases with displacement rate, whereas the strengthening contribution from voids decreases
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Aug 1983; 7 p; 3. topical meeting on fusion reactor materials; Albuquerque, NM (USA); 19-23 Sep 1983; CONF-830942--74; Available from NTIS, PC A02/MF A01; 1 as DE84004822
Record Type
Report
Literature Type
Conference; Numerical Data
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ALLOYS, AUSTENITIC STEELS, BARYON REACTIONS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, DATA, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HADRON REACTIONS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NUCLEAR REACTIONS, NUCLEON REACTIONS, NUMERICAL DATA, POWER REACTORS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SPECTRA, STAINLESS STEELS, STEELS
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