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In situ microtensile testing for ion beam irradiated materials

  • H. T. Vo
  • , A. Reinhardt
  • , D. Frazer
  • , N. Bailey
  • , P. Chou
  • , P. Hosemann

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

2 Scopus citations

Abstract

Understanding the changes in mechanical properties and failure mechanisms as a function of radiation damage is important for long-term operation of structural components in nuclear reactors. Due to the expense, the activation of the sample, and the long duration of neutron irradiation, ion beam irradiations (proton-irradiation and, increasingly, heavy-ion irradiation) are used as surrogates for neutron irradiation. However, the shallow irradiation depths of ion-beam irradiation have restricted mechanical property measurements until the recent advent of small-scale mechanical testing. In previous studies, nano-hardness and yield strength of proton-irradiated 304SS were measured using nanoindentation and in situ microcompression respectively. This study develops an in situ microtensile testing method to provide direct stress-strain curves, including the strain to failure, which previous studies do not provide. In addition, a novel way of quantifying irradiation-induced susceptibility to slip band formation in microscale specimens was demonstrated. Lastly, the paper introduces a new technique for measuring grain boundary strength, demonstrated on an oxidized grain boundary of Alloy 600 exposed to primary water chemistry environment.

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
Pages593-603
Number of pages11
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

  • Localized deformation
  • Micro-tensile testing
  • Primary water chemistry
  • Radiation damage
  • Slip band
  • Stainless steel
  • Stress corrosion cracking
  • Total elongation
  • Yield strength

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