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The Effect of Low Dose Rate Radiation on the Microchemistry of 304 Stainless Steel

Published online by Cambridge University Press:  15 February 2011

T. R. Allen
Affiliation:
Argonne National Laboratory-West, Idaho Falls, Idaho, USA
J. I. Cole
Affiliation:
Argonne National Laboratory-West, Idaho Falls, Idaho, USA
E. A. Kenik
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
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Abstract

As part of the shutdown of the EBR-II reactor, structural materials were retrieved to analyze the effect of long term, low dose rate irradiation. In this work, the effect of low dose rate (10 to 10−9 dpa/s) irradiation on grain boundary and void surface chemistry is analyzed. These dose rates are comparable to those in light water reactor structural components. The components were irradiated at 375-379°C, temperatures near the highest temperatures experienced in pressurized water reactors. Radiation-induced segregation (RIS) was measured on samples taken from 304 stainless steel hex ducts irradiated to doses between 10 and 12 dpa. Radiation-induced segregation is shown to vary with dose rate, with measured grain boundary chromium concentrations reaching as low as 5 at. % and nickel concentrations reaching as high as 33 at. %. For some radiation conditions, significant grain boundary precipitation occurs, possibly leaving components susceptible to environmental attack.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

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