SYMPOSIA PAPER Published: 01 January 2001
STP10547S

Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II

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Swelling behavior and microstructural evolution of 12% cold-worked 316 SS hexagonal ducts following irradiation in the outer rows of EBR-II is described. Immersion density measurements and transmission electron microscopy (TEM) examination were performed on a total of seven irradiation conditions. The samples were irradiated to temperatures between 375 and 430°C to doses between 23 and 51 dpa and at dose-rates ranging from 1.3 × 10-7 to 5.8 × 10-7 dpa/s. Dose-rates and temperatures approach conditions experienced by a variety of components in pressurized water reactors (PWR's) and those which may be present in future advanced reactors designs. TEM analysis was employed to elucidate the effect of radiation on the dislocation, void and precipitate structures as a function of irradiation conditions. A moderate dose-rate effect was observed for samples which were irradiated at dose-rates differing by a factor of two. Lower dose-rate samples contained voids of larger diameter and typically swelled more in the bulk. The dislocation and precipitate structure was not visibly influenced by a dose-rate decrease.

Author Information

Cole, JI
Argonne National Laboratory-West, Idaho Falls, ID
Allen, TR
Argonne National Laboratory-West, Idaho Falls, ID
Tsai, H
Argonne National Laboratory, Argonne, IL
Ukai, S
Japan Nuclear Cycle Development Institute, Ibaraki-Ken, Japan
Mizuta, S
Japan Nuclear Cycle Development Institute, Ibaraki-Ken, Japan
Akasaka, N
Japan Nuclear Cycle Development Institute, Ibaraki-Ken, Japan
Donomae, T
Japan Nuclear Cycle Development Institute, Ibaraki-Ken, Japan
Yoshitake, T
Japan Nuclear Cycle Development Institute, Ibaraki-Ken, Japan
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Details
Developed by Committee: E10
Pages: 413–426
DOI: 10.1520/STP10547S
ISBN-EB: 978-0-8031-5454-4
ISBN-13: 978-0-8031-2878-1