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Material property measurements from test reactor irradiations cannot always be applied directly to design reactor irradiation conditions because of differences in neutron spectra. A semi-empirical damage function can be derived from the test reactor data for a particular property to describe the damage effectiveness of neutrons as a function of their energies. Such functions have been derived for strength and ductility parameters of 20 percent cold-worked Type 316 stainless steel for irradiation temperatures of 393, 493, and 593°C (740, 920, and 1100°F). Both fast and thermal reactor data were used in the analysis. Quantitative conclusions from this analysis were limited by the lack of data; however, damage functions for tensile properties of 20 percent cold-worked Type 316 stainless steel irradiated at 393 and 493°C (740 and 920°F) appear to be consistent with the displacement cross section for stainless steel. At 593 °C (1100°F) the ductility damage functions show substantial deviation from the displacement cross shape when both fast and thermal reactors are included in the analysis. The latter damage functions were found to be consistent with the correlation of ductility with the square root of the product of displacements and helium concentration. Examples of application to fast reactors and fusion reactors are given.
radiation, radiation effects, cold working, stainless steels, displaced atoms, helium, tensile properties, swelling
Advanced scientist, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.