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Mechanical properties of neutron irradiated F82H using micro-tensile testing

Conference · · Nuclear Materials and Energy
Room temperature micro-tensile tests were successfully performed on F82H specimens neutron-irradiated at 573 K up to 5 dpa and unirradiated using a focused ion beam (FIB) device. Dimensions of the gauge section for micro-tensile specimens were about 10 µm (length) × 1 µm2 (area). These specimens were fabricated in a FIB device. The tensile properties obtained on specimens of micrometer size qualitatively agreed with results from millimeter size specimens. Using this micro-tensile testing technique is considered to become very useful data in combining the micro-tensile data on ion irradiated F82H with data on neutron irradiated material. This method overcomes the limitation on obtaining mechanical property on ion irradiated specimens to only micro-indentation testing.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1881173
Conference Information:
Journal Name: Nuclear Materials and Energy Journal Volume: 16
Country of Publication:
United States
Language:
English

References (6)

Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications journal June 2017
Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket journal October 2011
Depth-dependent nanoindentation hardness of reduced-activation ferritic steels after MeV Fe-ion irradiation journal October 2014
Relationship between nanohardness and microstructures in high-purity Fe–C as-quenched and quench-tempered martensite journal June 2003
Deformation Microstructure of a Reduced-Activation Ferritic/Martensitic Steel Irradiated in HFIR journal September 2003
Micro-mechanical investigation for effects of helium on grain boundary fracture of austenitic stainless steel journal February 2015

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