"Comparing structure-property evolution for PM-HIP and forged Alloy 625 irradiated with neutrons to 1 " Janelle Wharry, Caleb Clement, Sri Sowmya Panuganti, Patrick Warren, Yangyang Zhao, Yu Lu, Katelyn (Wheeler) Baird, David Frazer, Donna Guillen, David Gandy, Materials Science & Engineering A Vol. 857 2022 144058 Link | ||
"Comparing structure-property evolution for PM-HIP and forged alloy 625 irradiated with neutrons to 1 dpa"
Caleb Clement, Caleb Clement, Yangyang Zhao, Yu Lu, David Frazer, Donna Guillen, David Gandy, Janelle Wharry,
Materials Science and Engineering: A
Vol. 857
[unknown]
Link
The nuclear power industry has growing interest in qualifying powder metallurgy with hot isostatic pressing (PM-HIP) to replace traditional alloy fabrication methods for reactor structural components. But there is little known about the response of PM-HIP alloys to reactor conditions. This study directly compares the response of PM-HIP to forged Ni-base Alloy 625 under neutron irradiation doses ∼0.5–1 displacements per atom (dpa) at temperatures ranging ∼321–385 °C. Post-irradiation examination involves microstructure characterization, ASTM E8 uniaxial tensile testing, and fractography. Up through 1 dpa, PM-HIP Alloy 625 appears more resistant to irradiation-induced cavity nucleation than its forged counterpart, and consequently experiences significantly less hardening. This observed difference in performance can be explained by the higher initial dislocation density of the forged material, which represents an interstitial-biased sink that leaves a vacancy supersaturation to nucleate cavities. These findings show promise for qualification of PM-HIP Alloy 625 for nuclear applications, although higher dose studies are needed to assess the steady-state irradiated microstructure. |
||
"Comparison of ion irradiation effects in PM-HIP and forged alloy 625"
Caleb Clement, Patrick Warren, Yangyang Zhao, Xiang Liu, David Gandy, Janelle Wharry, Sichuang Xue,
Journal of Nuclear Materials
Vol. 558
[unknown]
Link
The nuclear industry has growing interest in replacing forgings with structural components fabricated by powder metallurgy with hot isostatic pressing (PM-HIP), owing to their chemical homogeneity, uniform grain structure, and near-net shape production. This study compares the ion irradiation response of PM-HIP and forged Alloy 625, over 50 and 100 dpa, 400 °C and 500 °C. Microstructure is characterized using down-zone bright-field scanning transmission electron microscopy (DZBFSTEM), and hardening is characterized using nanoindentation. PM-HIP Alloy 625 has a lower initial dislocation line density, resulting in a more rapid onset of dislocation loop growth and unfaulting than the forged material. But the total defect population (i.e. loop line length plus dislocation density) is insensitive to fabrication method. This finding shows promise for the eventual qualification of PM-HIP alloys for nuclear applications. |
||
"Comparison of ion irradiation effects in PM-HIP and forged alloy 625" Caleb Clement, Yangyang Zhao, Patrick Warren, Xiang Liu, Sichuang Xue, David Gandy, Janelle Wharry, Journal of Nuclear Materials Vol. 558 2022 Link | ||
"Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation" Janelle Wharry, Wen Jiang, Yangyang Zhao, Yu Lu, David Frazer, Donna Guillen, David Gandy, Journal of Nuclear Materials Vol. 594 2024 155018 Link | ||
"Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys"
Donna Guillen, Janelle Wharry, Caleb Clement, Yangyang Zhao, Katelyn Wachs, David Frazer, Jatuporn Burns, Yu Lu, Yaqiao Wu, Collin Knight, David Gandy,
Data in Brief
Vol. 48
2023
109092
Link
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. |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
Privacy and Accessibility · Vulnerability Disclosure Program