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In situ SEM push-to-pull micro-tensile testing of ex-service inconel X-750

  • C. Howard
  • , C. D. Judge
  • , H. T. Vo
  • , M. Griffiths
  • , P. Hosemann

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

1 Scopus citations

Abstract

A novel lift-out, push-to-pull, micro-tensile, small scale mechanical testing (SSMT) technique was developed to assess the yield strength, failure strength, and failure mechanisms of activated ex-service Inconel X-750 removed from the CANDU nuclear reactor core after extended service. Neutron irradiated Inconel X-750 components fail in an intergranular manner. Because these ex-service components are less than 1, mm in thickness, conventional tensile specimens cannot be fabricated from them. Thus, large-scale testing is not possible, and specimens on the order of 1, μm, ×, 1, μm, ×, 2.5, μm (thickness, ×, width, ×, gauge length) containing individual boundaries were fabricated in order to assess the grain boundary strength of the material as a function of irradiation temperature and dose. The variability introduced by differences in thermo-mechanical processing during fabrication was also assessed. Application of this new micro-tensile testing technique to non-irradiated Inconel X-750 gives good agreement with the bulk yield strength of the nickel superalloy, 1070, MPa. From SSMTs, the measured yield strengths of non-irradiated specimens were 1001, MPa at the outer edge and 1043, MPa at the center of the component. Cold work, introduced by grinding of the outside surface of the component, reduces ductility, as does irradiation. Initial tests indicate that away from the surface in the center, the boundary strength was reduced by ~456, MPa after irradiation to 78, dpa at an average irradiation temperature of 180, °C; the corresponding ductility decreased from 16.6 to, ≤2.3% total elongation. Testing is a work in progress and more tests are needed for higher precision with regards to grain boundary strength reduction.

Original languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
EditorsDenise Paraventi, Michael Wright, John H. Jackson
PublisherSpringer International Publishing
Pages743-757
Number of pages15
ISBN (Print)9783319672434
DOIs
StatePublished - 2018
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
Duration: Aug 13 2017Aug 17 2017

Publication series

NameMinerals, Metals and Materials Series
VolumePart F9
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/TerritoryUnited States
CityPortland
Period08/13/1708/17/17

Keywords

  • Grain boundary strength
  • Micro-tensile
  • Micromechanics
  • Small scale mechanical testing

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