TY - GEN
T1 - In situ SEM push-to-pull micro-tensile testing of ex-service inconel X-750
AU - Howard, C.
AU - Judge, C. D.
AU - Vo, H. T.
AU - Griffiths, M.
AU - Hosemann, P.
N1 - Publisher Copyright:
© The Minerals, Metals & Materials Society 2018.
PY - 2018
Y1 - 2018
N2 - 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.
AB - 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.
KW - Grain boundary strength
KW - Micro-tensile
KW - Micromechanics
KW - Small scale mechanical testing
UR - https://www.scopus.com/pages/publications/85042489412
U2 - 10.1007/978-3-319-67244-1_48
DO - 10.1007/978-3-319-67244-1_48
M3 - Conference contribution
AN - SCOPUS:85042489412
SN - 9783319672434
T3 - Minerals, Metals and Materials Series
SP - 743
EP - 757
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Paraventi, Denise
A2 - Wright, Michael
A2 - Jackson, John H.
PB - Springer International Publishing
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Y2 - 13 August 2017 through 17 August 2017
ER -