Microchemistry and microstructure evolution in proton-irradiated austenitic stainless steels

J. T. Busby, J. Gan, M. Daniels, G. S. Was, S. M. Bruemmer, D. J. Edwards, E. A. Kenik

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

The evolution of microchemistry and microstructure is examined in austenitic stainless steel alloys irradiated with 3.2 MeV protons up to doses of 3.0 dpa at 360°C and at a dose rate of 7 × 10-6 dpa/s. Measurements are compared to neutron-irradiation data obtained from the same heats of commercial-purity 304 and 316 stainless steels. Grain boundary composition was measured using scanning transmission electron microscopy with energy dispersive x-ray spectrometry (STEM-EDS) and dislocation loop microstructure was characterized using both bright and dark field imaging techniques on a transmission electron microscopy (TEM). The dose dependence of microchemical and microstructural changes was investigated at a temperature of 360°C for commercial purity (CP) 304 and 316 stainless steel alloys. Grain boundary composition measurements and segregation profiles from both the CP-304 and CP-316 are in excellent agreement (magnitude and profile shape) with those taken from the same heats irradiated with neutrons to comparable doses. Loop size distributions for both proton-irradiated heats are virtually identical to those for the neutron-irradiated heats, while the proton-irradiated dislocation densities are below those from neutron irradiation. Investigation of loop density measurement revealed that the dislocation loop densities measured at PNNL were a factor of 2 higher than those measured at UM in the same samples, primarily due to differences in the measurement technique and the instrument used. After accounting for differences in loop density measurement, the real difference in proton- and neutron-irradiated loop densities is less than a factor of 2 at higher doses. Radiation hardening in the proton-irradiated alloys, measured using Vickers indentation, tracks hardening induced by neutron irradiation very closely.

Original languageEnglish
Title of host publicationProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
EditorsS. Bruemmer, P. Ford, G. Was
PublisherMinerals, Metals and Materials Society
Pages1089-1097
Number of pages9
ISBN (Print)0873394755, 9780873394758
DOIs
StatePublished - 1999
Externally publishedYes
EventProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
Duration: Aug 1 1999Aug 5 1999

Publication series

NameProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Conference

ConferenceProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Country/TerritoryUnited States
CityNew Portbeach, CA
Period08/1/9908/5/99

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