NSUF - Nuclear Science User Facilities

David Frazer

Profile Information
Name
Dr. David Frazer
Institution
General Atomics
Position
Staff member
h-Index
ORCID
0000-0001-5139-858X
Expertise
Cladding, Mechanical Properties, Nanoindentation, Nuclear Fuel
Publications:
"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 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
"High-Temperature Nanoindentation of SiC/SiC Composites" David Frazer, JOM Vol. 72 2020 Link
The results of high-temperature nanoindentation testing on both a control and a neutron-irradiated silicon carbide matrix silicon carbide fiber composite sample are presented. The mechanical properties of the chemical vapor-infiltrated matrix were observed to have slightly increased in hardness and slightly decreased in elastic modulus after irradiation. Tyranno SA3 fiber behavior results are inconclusive, possibly because residual graphite in the fibers resulting from the manufacturing process produced a large scatter in the data. This work also demonstrates the capability to measure the individual components of fabricated composites at elevated temperature, which should provide inputs for modeling the macro-scale behavior of the composites.
"Materials qualification through the Nuclear Science User Facilities (NSUF): A case study on irradiated PM-HIP structural alloys" Janelle Wharry, Donna Guillen, Caleb Clement, Saquib Bin Habib, Wen Jiang, Yu Lu, Yaqiao Wu, Ching-Heng Shiau, David Frazer, Brenden Heidrich, Collin Knight, David Gandy, Frontiers in Nuclear Engineering Vol. 2 2023 1306529 Link
"Mechanical characteristics of SiC coating layer in TRISO fuel particles" Thak Sang Byun, David Frazer, Peter Hosemann, John Hunn, Maria Okuniewski, Kurt Terrani, Gokul Vasudevamurthy, J. N. Matros, Brian Jolly, Journal of Nuclear Materials Vol. 442 2013 133-142 Link
Tristructural isotropic (TRISO) particles are considered as advanced fuel forms for a variety of fission platforms. While these fuel structures have been tested and deployed in reactors, the mechanical properties of these structures as a function of production parameters need to be investigated in order to ensure their reliability during service. Nanoindentation techniques, indentation crack testing, and half sphere crush testing were utilized in order to evaluate the integrity of the SiC coating layer that is meant to prevent fission product release in the coated particle fuel form. The results are complimented by scanning electron microscopy (SEM) of the grain structure that is subject to change as a function of processing parameters and can alter the mechanical properties such as hardness, elastic modulus, fracture toughness and fracture strength. Through utilization of these advanced techniques, subtle differences in mechanical properties that can be important for in-pile fuel performance can be distinguished and optimized in iteration with processing science of coated fuel particle production.
"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.
"Microstructural and nanomechanical characterization of in-situ He implanted and irradiated fcc materials" David Frazer, Peter Hosemann, Djamel Kaoumi, Ce Zheng, Microscopy & Microanalysis Vol. 23 (Suppl 1) 2017 756-757 Link
"Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry" David Frazer, Journal of Nuclear Materials Vol. 516 2019 169-177 Link
Dense nanocrystalline and microcrystalline UO2 samples with controlled grain structure and stoichiometry were prepared by high energy ball milling and spark plasma sintering (SPS). Nano-indentation and micro-indentation testing were performed at different temperatures of 25 °C, 300 °C, and 600 °C in order to study the mechanical properties of the sintered fuels as functions of grain structure and temperature. Nanocrystalline UO2 display higher hardness than microcrystalline counterpart, consistent with the Hall-Petch strengthening mechanism. Greater Young's modulus and fracture toughness are also identified for the nanocrystalline UO2, and hardness and Young's modulus decrease with temperature, suggesting better ductility of oxide fuels at high temperature and small length scale. Hyper-stoichiometric UO2 specimen displays higher hardness and fracture toughness than stoichiometric UO2, due to the impediment of the crack propagation by the oxygen interstitial atoms. These results are useful in understanding the mechanical properties of the high burn-up structure (HBS) formed in nuclear fuels during reactor operation, and also provide critical experimental data as the input for the development and validation of the MARMOT fracture model of nuclear fuels.
"Role of low-level void swelling on plasticity and failure in a 33 dpa neutron-irradiated 304 stainless steel, International Journal of Plasticity " Frank Garner, Hi Vo, David Frazer, Aaron Kohnert, Sebastien Teysseyre, Saryu Fensin, Peter Hosemann, International Journal of Plasticity Vol. 164 2023 Link
"Twin boundary-accelerated ferritization of austenitic stainless steels in liquid lead–bismuth eutectic" David Frazer, Peter Hosemann, Konstantina Lambrinou, Erich Stergar, Scripta Materialia Vol. 118 2016 37-40 Link
Exposure of austenitic stainless steels to liquid lead-bismuth eutectic with low concentration of dissolved oxygen typically results in selective leaching of highly-soluble alloying elements and ferritization of the dissolution-affected zone. In this work, focused ion beam, transmission electron backscatter diffraction and scanning transmission electron microscopy were utilised to elucidate early-stage aspects of the dissolution corrosion process of cold-worked austenitic stainless steels exposed to static, oxygen-poor liquid lead-bismuth eutectic at 450C for 1000 hours. It was found that deformation-induced twin boundaries in the cold-worked steel bulk provide paths of accelerated penetration of the liquid metal into the steel bulk.
NSUF Articles:
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.5 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, May 14, 2018 - Calls and Awards
RTE 1st Call Awards Announced - Projects total approximately $1.4 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE-NE. Friday, February 8, 2019 - Calls and Awards
DOE awards 39 RTE Projects - Projects total approximately $1.3 million Thursday, February 1, 2018 - Calls and Awards
RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards
Additional Publications:
"Experimental Results of Conductive Inserts to Reduce Nuclear Fuel Temperature During Nuclear Volumetric Heating" Benjamin W. Spencer, Philip G. Petersen, Nicolas E. Woolstenhulme, David Ban, David Frazer, Laura Sudderth, Sarah Hamilton, James K. Jewell, Robert D. Mariani, Jason L. Schulthess, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.154176
"Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing" K. Wright, D. Frazer, K. Bawane, B. Kombaiah, W. Williams, S. Finkeldei, F. Teng, J. Giglio, M.N. Cinbiz, B. Hilton, J. Strumpell, R. Daum, K. Yueh, C. Jensen, D. Wachs, F. Cappia, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153881
"Small-scale mechanical testing and characterization of fuel cladding chemical interaction between HT9 cladding and advanced U-based metallic fuel alloy" David M. Frazer, Fabiola Cappia, Fei Teng, Daniel J. Murray, Tiankai Yao, Colin D. Judge, Jason M. Harp, Luca Capriotti, Yachun Wang, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153754
"High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)" B. Maiorov, U. Carvajal-Nuñez, J. Evans, E. Kardoulaki, J. Dunwoody, T.A. Saleh, J.T. White, D. Frazer, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153035
"Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX" A. Winston, B. Miller, B. Kombaiah, F. Teng, D. Murray, D. Frazer, J.M. Harp, F. Cappia, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152922
"In-Situ Transmission Electron Microscopy Microcantilever and Nanoindentation Testing of UO2" B. Shaffer, P. Peralta, P. Hosemann, D. Frazer, [2020] JOM · DOI: 10.1007/s11837-020-04102-x
"Report summarizing the setup and mechanical testing of bulk samples of doped UO2 reference samples" Michael Torrez, David Frazer, John Dunwoody, Darrin Byler, James Valdez, [2020] · DOI: 10.2172/1595642
"High-Temperature Nanoindentation of SiC/SiC Composites" C. P. Deck, P. Hosemann, D. Frazer, [2020] JOM · DOI: 10.1007/s11837-019-03860-7
"Evaluation of mechanical properties of 304 ss after proton irradiation using small scale mechanical testing" [2016] International Congress on Advances in Nuclear Power Plants, ICAPP 2016 · EID: 2-s2.0-84986229846
"Investigation of specimen size effects by in-situ microcompression of equal channel angular pressed copper" D. Frazer, A. Lupinacci, S. Parker, R.Z. Valiev, C. Shin, B. William Choi, P. Hosemann, C. Howard, [2016] Materials Science and Engineering A · DOI: 10.1016/j.msea.2015.09.110 · EID: 2-s2.0-84943608733
"Oxide scale formation on 316L and FeCrAl steels exposed to oxygen controlled static LBE at temperatures up to 800 °C" M.D. Abad, Y. Aussat, D. Frazer, A.J. Gubser, P. Hosemann, C. Cionea, [2016] Solar Energy Materials and Solar Cells · DOI: 10.1016/j.solmat.2015.09.007 · EID: 2-s2.0-84942475066
"Twin boundary-accelerated ferritization of austenitic stainless steels in liquid lead-bismuth eutectic" D. Frazer, E. Stergar, K. Lambrinou, P. Hosemann, [2016] Scripta Materialia · DOI: 10.1016/j.scriptamat.2016.02.029 · EID: 2-s2.0-84962219103
"Evaluation of the Mechanical Properties of Naturally Grown Multilayered Oxides Formed on HCM12A Using Small Scale Mechanical Testing" S. Parker, D. Frazer, M. Rebelo de Figueiredo, A. Lupinacci, K. Kikuchi, P. Hosemann, M. D. Abad, [2015] Oxidation of Metals · DOI: 10.1007/s11085-015-9551-6 · EID: 2-s2.0-84946474779
"Localized mechanical property assessment of SiC/SiC composite materials" M.D. Abad, D. Krumwiede, C.A. Back, H.E. Khalifa, C.P. Deck, P. Hosemann, D. Frazer, [2015] Composites Part A: Applied Science and Manufacturing · DOI: 10.1016/j.compositesa.2014.11.008 · EID: 2-s2.0-84920683973
"Lead-bismuth eutectic as a high temperature heat-transport fluid for thermal solar power" C. Cionea, M. Popovic, Y. Aussat, A. J. Gubser, P. Hosemann, D. Frazer, [2014] ASME 2014 8th International Conference on Energy Sustainability, ES 2014 Collocated with the ASME 2014 12th International Conference on Fuel Cell Science, Engineering and Technology · DOI: 10.1115/es2014-6528 · EID: 2-s2.0-84912126903

In order to increase the thermal efficiency and produce process heat for hydrogen production, the operating temperature of the heat-transfer fluid in thermal solar plants needs to increase, but to increase the operating temperature, new heat-transport liquids need to be evaluated. Liquid metals have been proposed as heat-transport fluids because of the large temperature ranges over which they remain liquid. One of the most studied liquid metals for non-solar applications has been lead-bismuth eutectic alloy (LBE), for the nuclear industry. The main challenge with using LBE as a coolant is that the major constituents of structural steels have high solubility in LBE. In this work, the challenges of using LBE as a high temperature heat-transport fluid are discussed, as well as initial results of high-temperature static corrosion tests of structural steels to evaluate their potential use in a thermal solar power plant.
"Multi scale characterization of SiC/SiC composite materials" [2014] TMS Annual Meeting · EID: 2-s2.0-84899693303
"Accident tolerant refractory metal based cladding for light water reactors" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902803155
"Essential aspects of controlling the oxygen content of molten tin in engineering applications" Aditya Prahlad Shivprasad, David Frazer, Peter Hosemann, Alan Michael Bolind, [2013] Materials and Design · DOI: 10.1016/j.matdes.2013.04.096 · EID: 2-s2.0-84879242230
"Liquid metal as a heat transport fluid for thermal solar power applications" E. Stergar, C. Cionea, P. Hosemann, D. Frazer, [2013] Energy Procedia · DOI: 10.1016/j.egypro.2014.03.068 · EID: 2-s2.0-84902275400
"Mechanical characteristics of SiC coating layer in TRISO fuel particles" J.N. Martos, D. Frazer, G. Vasudevamurthy, T.S. Byun, J.D. Hunn, B.C. Jolly, K. Terrani, M. Okuniewski, P. Hosemann, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.08.041 · EID: 2-s2.0-84884510336
Source: ORCID/CrossRef using DOI

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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.

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