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Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence

  • Tsunemitsu Yoshitake
  • , Takako Donomae
  • , Shunji Mizuta
  • , Hanchung Tsai
  • , Robert V. Strain
  • , Todd R. Allen
  • , James I. Cole

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

2 Scopus citations

Abstract

The effects of lower-dose-rate irradiation on the tensile properties of 12% cold-worked type 316 stainless steel hexagonal ducts which were irradiated in the outer rows of EBR-II were investigated. Tension tests were conducted on a total of seventeen irradiation conditions. Fractographic examinations were performed on four irradiation conditions which were selected based on the results of tension tests. The results of the tension tests and fractographic examinations showed that the 316 stainless steel hexagonal ducts exhibited irradiation hardening typical to 316 stainless steels irradiated at similar temperatures and retained respectable ductility after the irradiation. There was no significant effect of dose rate on tensile properties for the range of irradiation conditions of this study.

Original languageEnglish
Title of host publicationEffects of Radiation on Materials
Subtitle of host publication20th International Symposium
EditorsStan T. Rosinski, Martin L. Grossbeck, Todd R. Allen, Arvind S. Kumar
PublisherASTM International
Pages469-486
Number of pages18
ISBN (Electronic)9780803128781
DOIs
StatePublished - 2001
Externally publishedYes
Event20th International Symposium on Effects of Radiation on Materials 2000 - Williamsburg, United States
Duration: Jun 6 2000Jun 8 2000

Publication series

NameASTM Special Technical Publication
VolumeSTP 1405
ISSN (Print)0066-0558

Conference

Conference20th International Symposium on Effects of Radiation on Materials 2000
Country/TerritoryUnited States
CityWilliamsburg
Period06/6/0006/8/00

Keywords

  • 12% cold-worked type 316 stainless steel
  • EBR-H reflector duct
  • ductility
  • failure mode
  • fast reactor core material
  • lower-dose-rate irradiation
  • strength
  • tensile properties

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