Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys
Janelle P. Wharry,
Caleb D. Clement,
Yangyang Zhao,
Katelyn Baird,
David Frazer,
Jatuporn Burns,
Yu Lu,
Yaqiao Wu,
Collin Knight,
Donna P. Guillen,
David W. Gandy
Affiliations
Janelle P. Wharry
School of Materials Engineering, Purdue University, 205 Gates Rd., West Lafayette, IN 47906, USA; Corresponding author.
Caleb D. Clement
School of Materials Engineering, Purdue University, 205 Gates Rd., West Lafayette, IN 47906, USA
Yangyang Zhao
School of Materials Engineering, Purdue University, 205 Gates Rd., West Lafayette, IN 47906, USA
Katelyn Baird
Idaho National Laboratory, 1955 N Fremont Ave., Idaho Falls, ID 83415, USA
David Frazer
Idaho National Laboratory, 1955 N Fremont Ave., Idaho Falls, ID 83415, USA
Jatuporn Burns
Idaho National Laboratory, 1955 N Fremont Ave., Idaho Falls, ID 83415, USA
Yu Lu
Center for Advanced Energy Studies, 995 M.K. Simpson Blvd., Idaho Falls, ID 83401, USA
Yaqiao Wu
Center for Advanced Energy Studies, 995 M.K. Simpson Blvd., Idaho Falls, ID 83401, USA; Micron School of Materials Science & Engineering, Boise State University, 1437 W University Dr., Boise, ID 83706, USA
Collin Knight
Idaho National Laboratory, 1955 N Fremont Ave., Idaho Falls, ID 83415, USA
Donna P. Guillen
Idaho National Laboratory, 1955 N Fremont Ave., Idaho Falls, ID 83415, USA
David W. Gandy
Electric Power Research Institute, 1300 W W.T. Harris Blvd., Charlotte, NC 28262, USA
This article presents the comprehensive mechanical testing data archive from a neutron irradiation campaign of nuclear structural alloys fabricated by powder metallurgy with hot isostatic pressing (PM-HIP). The irradiation campaign was designed to facilitate a direct comparison of PM-HIP to conventional casting or forging. Five common nuclear structural alloys were included in the campaign: 316L stainless steel, SA508 pressure vessel steel, Grade 91 ferritic steel, and Ni-base alloys 625 and 690. Irradiations were carried out in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to target doses of 1 and 3 displacements per atom (dpa) at target temperatures of 300 and 400 °C. This article contains the data collected from post-irradiation uniaxial tensile tests following ASTM E8 specifications, fractography of these tensile bars, and nanoindentation. By making this systematic and valuable neutron irradiated mechanical behavior dataset openly available to the nuclear materials research community, researchers may now use this data to populate material performance databases, validate material performance and hardening models, design follow-on experiments, and enable future nuclear code-qualification of PM-HIP techniques.
