Donna Post Guillen, PhD, PE, has over 30 years of research and engineering experience and has served as Principal Investigator for numerous multidisciplinary projects encompassing energy systems, nuclear reactor fuels and materials experiments, and wasteform development. She is experienced with X-ray and neutron beamline experiments, computational methods, tools and software for data analysis, visualization, application development, machine learning and informatics, simulation, design, and programming. Her core area of expertise is thermal fluids, computational fluid dynamics and heat transfer analysis. She has performed irradiation testing of new materials and thermal analysis for nuclear reactor experiments in her role as Principal Investigator/Technical Lead for the DOE Nuclear Science User Facility Program. She is the lead inventor on two patents for a new metal matrix material to produce a fast neutron flux environment within a pressurized water reactor. She actively mentors students, routinely chairs and organizes technical meetings for professional societies, serves in leadership capacity for the American Nuclear Society (Thermal Hydraulics Executive and Program Committees), The Minerals, Metals and Materials Society (former Chair of the TMS Energy Committee, JOM Advisor) and the American Society of Mechanical Engineers (Thermal Hydraulics and Computational Fluid Dynamic Studies Track Co-Chair), provides subject matter reviews for proposals and technical manuscripts, has published over 100 papers and received two Best Paper awards, authored technical reports and journal articles, and written/edited three books.
"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. |
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"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 | ||
"Experiment design for the neutron irradiation of PM-HIP alloys for nuclear reactors" Donna Guillen, Janelle Wharry, Gregory Housley, Cody Hale, Jason Brookman, David Gandy, Nuclear Engineering and Design Vol. 402 2023 Link | ||
"High conduction neutron absorber to simulate fast reactor environment in an existing test reactor"
Donna Guillen, Larry Greenwood, James Parry,
Journal of Radioanalytical and Nuclear Chemistry
Vol. 302
2014
413-424
Link
A new metal matrix composite material has been developed to serve as a thermal neutron absorber for testing fast reactor fuels and materials in an existing pressurized water reactor. The performance of this material was evaluated by placing neutron fluence monitors within shrouded and unshrouded holders and irradiating for up to four cycles. The monitor wires were analyzed by gamma and X-ray spectrometry to determine the activities of the activation products. Adjusted neutron fluences were calculated and grouped into three bins—thermal, epithermal, and fast—to evaluate the spectral shift created by the new material. A comparison of shrouded and unshrouded fluence monitors shows a thermal fluence decrease of *11% for the shielded monitors. Radioisotope activity and mass for each of the major activation products is given to provide insight into the evolution of thermal absorption cross section during irradiation. The thermal neutron absorption capability of the composite material appears to diminish at total neutron fluence levels of*8 9 1025 n/m2. Calculated
values for dpa in excess of 2.0 were obtained for two common structural materials (iron and nickel) of interest for future fast flux experiments. |
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"Impact of neutron irradiation on the thermophysical properties of additively manufactured stainless steel and inconel" Mark Graham, Jeffrey King, Tsvetoslav Pavlov, Cynthia Adkins, Scott Middlemas, Donna Guillen, Journal of Nuclear Materials Vol. 549 2021 Link | ||
"In situ tensile study of PM-HIP and wrought 316L stainless steel and Inconel 625 alloys with high energy diffraction microscopy" Janelle Wharry, Donna Guillen, Elizabeth Getto, Darren Pagan, Materials Science & Engineering A Vol. 738 2018 380-388 Link | ||
"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 | ||
"Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material"
Donna Guillen, William Harris,
Metallurgical and Materials Transactions E
Vol. 3
2016
123-133
Link
A metal matrix composite (MMC) material composed of hafnium aluminide (Al3Hf) intermetallic particles in an aluminum matrix has been identified as a promising material for fast flux irradiation testing applications. This material can filter thermal neutrons while simultaneously providing high rates of conductive cooling for experiment capsules. The purpose of this work is to investigate effects of Hf-Al material composition and neutron irradiation on thermophysical properties, which were measured before and after irradiation. When performing differential scanning calorimetry (DSC) on the irradiated specimens, a large exotherm corresponding to material annealment was observed. Therefore, a test procedure was developed to perform DSC and laser flash analysis (LFA) to obtain the specific heat and thermal diffusivity of pre- and post-annealment specimens. This paper presents the thermal properties for three states of the MMC material: (1) unirradiated, (2) as-irradiated, and (3) irradiated and annealed. Microstructure-property relationships were obtained for the thermal conductivity. These relationships are useful for designing components from this material to operate in irradiation environments. The ability of this material to effectively conduct heat as a function of temperature, volume fraction Al3Hf, radiation damage, and annealing is assessed using the MOOSE suite of computational tools. |
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"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. |
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"Microstructure of Neutron-Irradiated Al3Hf-Al Thermal Neutron Absorber Materials"
Donna Guillen,
MDPI Materials
Vol. Vol 18 Issue 4
2025
Link
A thermal neutron-absorbing metal matrix composite (MMC) comprised of Al3Hf particles in an aluminum matrix was developed to filter out thermal neutrons and create a fast flux environment for material testing in a mixed-spectrum nuclear reactor. Intermetallic Al3Hf particles capture thermal neutrons and are embedded in a highly conductive aluminum matrix that provides conductive cooling of the heat generated due to thermal neutron capture by the hafnium. These Al3Hf-Al MMCs were fabricated using powder metallurgy via hot pressing. The specimens were neutron-irradiated to between 1.12 and 5.38 dpa and temperatures ranging from 286 °C to 400 °C. The post-irradiation examination included microstructure characterization using transmission electron microscopy (TEM) and energy-dispersive X-ray spectroscopy. This study reports the microstructural observations of four irradiated samples and one unirradiated control sample. All the samples showed the presence of oxide at the particle–matrix interface. The irradiated specimens revealed needle-like structures that extended from the surface of the Al3Hf particles into the Al matrix. An automated segmentation tool was implemented based on a YOLO11 computer vision-based approach to identify dislocation lines and loops in TEM images of the irradiated Al-Al3Hf MMCs. This work provides insight into the microstructural stability of Al3Hf-Al MMCs under irradiation, supporting their consideration as a novel neutron absorber that enables advanced spectral tailoring. |
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"Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials"
Donna Guillen, Mychailo Toloczko, Ramprashad Prabhakaran, Yuanyuan Zhu, Yu Lu, Yaqiao Wu,
Materials
Vol. 16
2023
5518
Link
thermal neutron absorber material composed of Al3Hf particles in an aluminum matrix is under development for the Advanced Test Reactor. This metal matrix composite was fabricated via hot pressing of high-purity aluminum and micrometer-size Al3Hf powders at volume fractions of 20.0, 28.4, and 36.5%. Room temperature tensile and hardness testing of unirradiated specimens revealed a linear relationship between volume fraction and strength, while the tensile data showed a strong decrease in elongation between the 20 and 36.5% volume fraction materials. Tensile tests conducted at 200 °C on unirradiated material revealed similar trends. Evaluations were then conducted on specimens irradiated at 66 to 75 °C to four dose levels ranging from approximately 1 to 4 dpa. Tensile properties exhibited the typical increase in strength and decrease in ductility with dose that are common for metallic materials irradiated at ≤0.4Tm. Hardness also increased with neutron dose. The difference in strength between the three different volume fraction materials was roughly constant as the dose increased. Nanoindentation measurements of Al3Hf particles in the 28.4 vol% material showed the expected trend of increased hardness with irradiation dose. Transmission electron microscopy revealed oxygen at the interface between the Al3Hf particles and aluminum matrix in the irradiated material. Scanning electron microscopy of the exterior surface of tensile tested specimens revealed that deformation of the material occurs via plastic deformation of the Al matrix, cracking of the Al3Hf particles, and to a lesser extent, tearing of the matrix away from the particles. The fracture surface of an irradiated 28.4 vol% specimen showed failure by brittle fracture in the particles and ductile tearing of the aluminum matrix with no loss of cohesion between the particles and matrix. The coefficient of thermal expansion decreased upon irradiation, with a maximum change of −6.3% for the annealed irradiated 36.5 vol% specimen. |
"Microstructure of Aluminum Matrix in Composite Absorber Block Material" Donna Guillen, TMS 2014 February 16-20, (2014) | |
"Neutron Irradiation of Nuclear Structural Materials Fabricated by Powder Metallurgy with Hot Isostatic Pressing" David Gandy, Donna Guillen, Janelle Wharry, 2017 ANS Annual Meeting [unknown] |
"Refractory wettability and surface tension of several nuclear waste glass simulants" Daniel Yankura, Michael V. Glazoff, Tongan Jin, Albert A. Kruger, Donna Post Guillen, [2025] Materials Letters · DOI: 10.1016/j.matlet.2024.137880 | |
"Microstructure of Neutron-Irradiated Al3Hf-Al Thermal Neutron Absorber Materials"
Janelle Wharry, Yu Lu, Michael Wu, Jeremy Sharapov, Matthew Anderson, Donna Post Guillen,
[2025]
Materials
· DOI: 10.3390/ma18040833
A thermal neutron-absorbing metal matrix composite (MMC) comprised of Al3Hf particles in an aluminum matrix was developed to filter out thermal neutrons and create a fast flux environment for material testing in a mixed-spectrum nuclear reactor. Intermetallic Al3Hf particles capture thermal neutrons and are embedded in a highly conductive aluminum matrix that provides conductive cooling of the heat generated due to thermal neutron capture by the hafnium. These Al3Hf-Al MMCs were fabricated using powder metallurgy via hot pressing. The specimens were neutron-irradiated to between 1.12 and 5.38 dpa and temperatures ranging from 286 °C to 400 °C. The post-irradiation examination included microstructure characterization using transmission electron microscopy (TEM) and energy-dispersive X-ray spectroscopy. This study reports the microstructural observations of four irradiated samples and one unirradiated control sample. All the samples showed the presence of oxide at the particle–matrix interface. The irradiated specimens revealed needle-like structures that extended from the surface of the Al3Hf particles into the Al matrix. An automated segmentation tool was implemented based on a YOLO11 computer vision-based approach to identify dislocation lines and loops in TEM images of the irradiated Al-Al3Hf MMCs. This work provides insight into the microstructural stability of Al3Hf-Al MMCs under irradiation, supporting their consideration as a novel neutron absorber that enables advanced spectral tailoring. |
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"Microstructure of Neutron-Irradiated Al3Hf-Al Thermal Neutron Absorber Materials"
Janelle Wharry, Yu Lu, Michael Wu, Jeremy Sharapov, Matthew Anderson, Donna Post Guillen,
[2025]
Materials
· DOI: 10.3390/ma18040833
A thermal neutron-absorbing metal matrix composite (MMC) comprised of Al3Hf particles in an aluminum matrix was developed to filter out thermal neutrons and create a fast flux environment for material testing in a mixed-spectrum nuclear reactor. Intermetallic Al3Hf particles capture thermal neutrons and are embedded in a highly conductive aluminum matrix that provides conductive cooling of the heat generated due to thermal neutron capture by the hafnium. These Al3Hf-Al MMCs were fabricated using powder metallurgy via hot pressing. The specimens were neutron-irradiated to between 1.12 and 5.38 dpa and temperatures ranging from 286 °C to 400 °C. The post-irradiation examination included microstructure characterization using transmission electron microscopy (TEM) and energy-dispersive X-ray spectroscopy. This study reports the microstructural observations of four irradiated samples and one unirradiated control sample. All the samples showed the presence of oxide at the particle–matrix interface. The irradiated specimens revealed needle-like structures that extended from the surface of the Al3Hf particles into the Al matrix. An automated segmentation tool was implemented based on a YOLO11 computer vision-based approach to identify dislocation lines and loops in TEM images of the irradiated Al-Al3Hf MMCs. This work provides insight into the microstructural stability of Al3Hf-Al MMCs under irradiation, supporting their consideration as a novel neutron absorber that enables advanced spectral tailoring. |
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"Modeling Approach for the Aluminum-clad Dry Storage Pilot using HFIR Fuel" Donna Guillen, [2024] · DOI: 10.2172/2448230 | |
"Critical Review of LPBF Metal Print Defects Detection: Roles of Selective Sensing Technology"
Scott Wahlquist, Amir Ali, Donna Guillen,
[2024]
Applied Sciences
· DOI: 10.3390/app14156718
· ISSN: 2076-3417
The integrative potential of LPBF-printed parts for various innovative applications depends upon the robustness and infallibility of the part quality. Eliminating or sufficiently reducing factors contributing to the formation of defects is an integral step to achieving satisfiable part quality. Significant research efforts have been conducted to understand and quantify the triggers and origins of LPBF defects by investigating the material properties and process parameters for LPBF-printed geometries using various sensing technologies and techniques. Frequently, combinations of sensing techniques are applied to deepen the understanding of the investigated phenomena. The main objectives of this review are to cover the roles of selective sensing technologies by (1) providing a summary of LPBF metal print defects and their corresponding causes, (2) informing readers of the vast number and types of technologies and methodologies available to detect defects in LPBF-printed parts, and (3) equipping readers with publications geared towards defect detection using combinations of sensing technologies. Due to the large pool of developed sensing technology in the last few years for LPBF-printed parts that may be designed for targeting a specific defect in metal alloys, the article herein focuses on sensing technology that is common and applicable to most common defects and has been utilized in characterization for an extended period with proven efficiency and applicability to LPBF metal parts defect detection. |
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"CFD model for predicting spent nuclear fuel drying conditions"
Nathaniel Cooper, Alexander W. Abboud, Tanvir Farouk, Jamil Khan, Donna Post Guillen, Travis Knight, Fakhrul Islam,
[2024]
Nuclear Science and Technology Open Research
· DOI: 10.12688/nuclscitechnolopenres.17492.1
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"Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation" Yangyang Zhao, Yu Lu, Yaqiao Wu, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, Wen Jiang, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155018 | |
"Characterizing the microstructures of mammalian enamel by synchrotron phase contrast microCT" J.R. Grimm, C. Renteria, D.P. Guillen, K. Tang, V. Nikitin, D.D. Arola, C. Marsico, [2024] Acta Biomaterialia · DOI: 10.1016/j.actbio.2024.02.038 | |
"Effect of climate and component performance on optimized recuperated air Brayton cycles for nuclear microreactor power conversion" D.P. Guillen, M.G. McKellar, [2023] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2023.104761 | |
"Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys" Caleb D. Clement, Yangyang Zhao, Katelyn Baird, David Frazer, Jatuporn Burns, Yu Lu, Yaqiao Wu, Collin Knight, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, [2023] Data in Brief · DOI: 10.1016/j.dib.2023.109092 | |
"Conversion degree and heat transfer in the cold cap and their effect on glass production rate in an electric melter"
Pavel Hrma, Alexander Abboud, Donna Post Guillen, Miroslava Vernerová, Jaroslav Kloužek, Mark Hall, Albert A. Kruger, Richard Pokorný, Pavel Ferkl,
[2023]
International Journal of Applied Glass Science
· DOI: 10.1111/ijag.16615
A predictive model of melt rate in waste glass vitrification operations is needed to inform melter operations during normal and off‐normal operations. This paper describes the development of a model of the cold cap (the reacting melter feed floating on molten glass in a glass melter) that couples heat transfer with the feed‐to‐glass conversion kinetics. The model was applied to four melter feeds designed for high‐level and low‐activity nuclear waste feeds using the material properties, either measured or estimated, to obtain temperature and conversion distribution within the cold cap. The cold cap model, when coupled with a computational fluid dynamics model of a Joule‐heated glass melter, allows the prediction of the glass production rate and power consumption. The results show reasonable agreement with the melting rates measured during pilot‐scale melter tests. |
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"Nonnuclear Experimental Capabilities to Support Design, Development, and Demonstration of Microreactors" J. L. Hartvigsen, T. J. Morton, J. Yoo, S. Qin, M. Song, D. P. Guillen, T. Unruh, J. E. Hansel, J. Jackson, J. Gehin, H. Trellue, D. Mascarenas, R. S. Reid, C. M. Petrie, P. Sabharwall, [2023] Nuclear Technology · DOI: 10.1080/00295450.2022.2043087 | |
"Review of Passive Heat Removal Strategies for Nuclear Microreactor Systems" Donna Post Guillen, [2023] Nuclear Technology · DOI: 10.1080/00295450.2022.2055701 | |
"Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications" Clayton G. Turner, Donna Post Guillen, [2022] Nuclear Technology · DOI: 10.1080/00295450.2021.1977085 | |
"An evaluation of power conversion systems for land-based nuclear microreactors: Can aeroderivative engines facilitate near-term deployment?" P.J. McDaniel, D.P. Guillen, [2022] Nuclear Engineering and Technology · DOI: 10.1016/j.net.2021.10.010 | |
"Technical feasibility of integrating a modified power conversion unit into a non‐nuclear microreactor testbed" Daniel S. Wendt, Donna Post Guillen, [2021] International Journal of Energy Research · DOI: 10.1002/er.6517 | |
"DOE Microreactor Program: Summary of Experimental Capabilities Development and Activities" Holly Trellue, Jeremy Hartvigsen, Terry Morton, Donna Guillen, Yasir Arafat, Theresa Cutler, Keith Jewell, Erik Luther, Robert Reid, Chase Taylor, Troy Unruh, Chris Petrie, David Mascarenas, Peter Meyerhoffer, James Jewell, Jess Gehin, John Jackson, Piyush Sabharwall, [2021] · DOI: 10.2172/1824347 | |
"Experimental Capabilities to Support Design, Development and Demonstration of Microreactors" Jeremy Hartvigsen, Terry Morton, Donna Guillen, Troy Unruh, John Jackson, Jess Gehin, H. Trellue, D. Mascarenas, R. Reid, Piyush Sabharwall, [2021] · DOI: 10.2172/2371663 | |
"Heat transfer from glass melt to cold cap: Computational fluid dynamics study of cavities beneath cold cap"
Donna P. Guillen, Pavel Hrma, Albert A. Kruger, Jaroslav Klouzek, Richard Pokorny, Alexander W. Abboud,
[2021]
International Journal of Applied Glass Science
· DOI: 10.1111/ijag.15863
Efficient glass production depends on the continuous supply of heat from the glass melt to the floating layer of batch, or cold cap. Computational fluid dynamics (CFD) are employed to investigate the formation and behavior of gas cavities that form beneath the batch by gases released from the collapsing primary foam bubbles, ascending secondary bubbles, and in the case of forced bubbling, from the rising bubbling gas. The gas phase fraction, temperature, and velocity distributions below the cold cap are used to calculate local and average heat transfer rates as a function of the bubbling rate. It is shown that the thickness of the cavities is nearly independent of the cold cap shape and the amount of foam evolved during batch conversion. It is ~7 mm and up to ~15 mm for the cases without and with forced bubbling used to promote circulation within the melt, respectively. Using computed velocity and temperature profiles, the melting rate of the simulated high‐level nuclear waste glass batch was estimated to increase with the bubbling rate to the power of ~0.3 to 0.9, depending on the flow pattern. The simulation results are in good agreement with experimental data from laboratory‐ and pilot‐scale melter tests. |
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"Machine Learning Applications in Advanced Manufacturing Processes" Donna Post Guillen, [2020] JOM · DOI: 10.1007/s11837-020-04380-5 | |
"An Applied Strategy for Using Empirical and Hybrid Models in Online Monitoring" Hany Abdel-Khalik, Kellen Giraud, L. Griffel, Donna Guillen, Athi Varuttamaseni, Ahmad Al Rashdan, [2020] · DOI: 10.2172/2376854 | |
"Integration of a Microturbine Power Conversion Unit in MAGNET" Daniel Wendt, Donna Guillen, [2020] · DOI: 10.2172/1736010 | |
"Effect of cold cap coverage and emissivity on the plenum temperature in a pilot‐scale waste vitrification melter"
Donna P. Guillen, Richard Pokorny, Alexander W. Abboud,
[2020]
International Journal of Applied Glass Science
· DOI: 10.1111/ijag.15031
Integrated computational fluid dynamics (CFD) models are being developed to model the complex physics occurring within the high‐level waste melter for vitrification of legacy tank waste at the Hanford site. This study presents a validation of the integrated CFD model by using data from two experimental runs in a pilot‐scale melter. While the model uses several simplifying assumptions (such as constant heat sinks from a cooling jacket and inleakage of ambient air, steady state feed‐to‐batch conversion heat, and a cold cap model with a simplified shape), it closely predicts the molten glass (1150°C and 1175°C) and plenum temperatures (550°C) obtained from thermocouples during two pilot‐scale tests, with an average cold cap coverage of 80%. Additional simulations were performed to explore the sensitivity of the predicted plenum temperatures to variations in cold cap coverage (fraction of melt surface covered by the glass batch) and batch emissivity. The plenum temperature was found to be in the range of 606°C when cold cap coverage decreased from 95% to 70%. Cold cap emissivity had a smaller effect, increasing the plenum temperature by as much as 179°C when cold cap emissivity increased from 0.2 to 0.8. Maintaining a high cold cap coverage without overfeeding is important for a sustained melter operation with high glass throughput. This work provides a tool for achieving that goal in terms of correlating the plenum temperature with the cold cap coverage. |
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"Evolution of chromium, manganese and iron oxidation state during conversion of nuclear waste melter feed to molten glass" S. Lee, P. Hrma, J. Traverso, R. Pokorny, J. Klouzek, A.A. Kruger, D.P. Guillen, [2020] Journal of Non-Crystalline Solids · DOI: 10.1016/j.jnoncrysol.2019.119860 | |
"An Algorithm to Generate Synthetic 3D Microstructures from 2D Exemplars" Donna Post Guillen, William H. Harris, Tristan N. Ashton, [2020] JOM · DOI: 10.1007/s11837-019-03825-w | |
"Crystallization behavior of iron‐ and boron‐containing nepheline (Na2O·Al2O3·2SiO2) based model high‐level nuclear waste glasses"
Mostafa Ahmadzadeh, Alex Scrimshire, Edmund Han, Paul A. Bingham, Donna Guillen, John McCloy, Ashutosh Goel, Ambar Deshkar,
[2019]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.15936
This study focuses on understanding the relationship between iron redox, composition, and heat‐treatment atmosphere in nepheline‐based model high‐level nuclear waste glasses. Glasses in the Na2O–Al2O3–B2O3–Fe2O3–SiO2system with varying Al2O3/Fe2O3and Na2O/Fe2O3ratios have been synthesized by melt‐quench technique and studied for their crystallization behavior in different heating atmospheres—air, inert (N2), and reducing (96%N2–4%H2). The compositional dependence of iron redox chemistry in glasses and the impact of heating environment and crystallization on iron coordination in glass‐ceramics have been investigated by Mössbauer spectroscopy and vibrating sample magnetometry. While iron coordination in glasses and glass‐ceramics changed as a function of glass chemistry, the heating atmosphere during crystallization exhibited minimal effect on iron redox. The change in heating atmosphere did not affect the phase assemblage but did affect the microstructural evolution. While glass‐ceramics produced as a result of heat treatment in air and N2atmospheres developed a golden/brown colored iron‐rich layer on their surface, those produced in a reducing atmosphere did not exhibit any such phenomenon. Furthermore, while this iron‐rich layer was observed in glass‐ceramics with varying Al2O3/Fe2O3ratio, it was absent from glass‐ceramics with varying Na2O/Fe2O3ratio. An explanation of these results has been provided on the basis of kinetics of diffusion of oxygen and network modifiers in the glasses under different thermodynamic conditions. The plausible implications of the formation of iron‐rich layer on the surface of glass‐ceramics on the chemical durability of high‐level nuclear waste glasses have been discussed. |
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"Crystallization behavior of iron- and boron-containing nepheline (Na This study focuses on understanding the relationship between iron redox, composition, and heat‐treatment atmosphere in nepheline‐based model high‐level nuclear waste glasses. Glasses in the Na2O–Al2O3–B2O3–Fe2O3–SiO2system with varying Al2O3/Fe2O3and Na2O/Fe2O3ratios have been synthesized by melt‐quench technique and studied for their crystallization behavior in different heating atmospheres—air, inert (N2), and reducing (96%N2–4%H2). The compositional dependence of iron redox chemistry in glasses and the impact of heating environment and crystallization on iron coordination in glass‐ceramics have been investigated by Mössbauer spectroscopy and vibrating sample magnetometry. While iron coordination in glasses and glass‐ceramics changed as a function of glass chemistry, the heating atmosphere during crystallization exhibited minimal effect on iron redox. The change in heating atmosphere did not affect the phase assemblage but did affect the microstructural evolution. While glass‐ceramics produced as a result of heat treatment in air and N2atmospheres developed a golden/brown colored iron‐rich layer on their surface, those produced in a reducing atmosphere did not exhibit any such phenomenon. Furthermore, while this iron‐rich layer was observed in glass‐ceramics with varying Al2O3/Fe2O3ratio, it was absent from glass‐ceramics with varying Na2O/Fe2O3ratio. An explanation of these results has been provided on the basis of kinetics of diffusion of oxygen and network modifiers in the glasses under different thermodynamic conditions. The plausible implications of the formation of iron‐rich layer on the surface of glass‐ceramics on the chemical durability of high‐level nuclear waste glasses have been discussed. |
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"Computational experiments to characterize bubble formation and movement in waste glass foam layer" [2019] 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 · EID: 2-s2.0-85073720830 | |
"Investigation of Performance Enhancements for Air Brayton/ORC Combined Cycles for Small (~ 2 MWe) Power Systems and a Moderate Heat Source Temperature" Donna Post Guillen, Michael McKellar, Joseph Litrel, [2019] JOM · DOI: 10.1007/s11837-018-3257-6 · EID: 2-s2.0-85058081458 | |
"Particle settling in a simulated melter discharge riser" Alexander W. Abboud, Kevin Fox, Donna Post Guillen, [2019] Materials Letters · DOI: 10.1016/j.matlet.2018.10.028 · EID: 2-s2.0-85054783295 | |
"Preface" [2019] Minerals, Metals and Materials Series · EID: 2-s2.0-85064761150 | |
"Sensitivity study of forced convection bubbling in a transparent viscous fluid as a proxy for molten borosilicate glass" Alexander W. Abboud, Donna Post Guillen, [2019] Annals of Nuclear Energy · DOI: 10.1016/j.anucene.2018.10.046 · EID: 2-s2.0-85055496255 | |
"Development of a Validation Approach for an Integrated Waste Glass Melter Model" Alexander W. Abboud, Richard Pokorny, William C. Eaton, Derek Dixon, Kevin Fox, Albert A. Kruger, Donna Post Guillen, [2018] Nuclear Technology · DOI: 10.1080/00295450.2018.1458559 | |
"An Eco-Friendly System for the Production of Value-Added Materials from Dairy Manure" Erik R. Coats, Armando G. McDonald, Kevin Feris, Donna Post Guillen, [2018] Journal of Materials · DOI: 10.1007/s11837-018-2995-9 | |
"A methodology to reduce the computational cost of transient multiphysics simulations for waste vitrification" Donna Post Guillen, Alexander W. Abboud, [2018] Computers & Chemical Engineering · DOI: 10.1016/j.compchemeng.2018.03.027 | |
"Effect of glass viscosity on foaming behavior and heat transfer in a laboratory-scale waste glass melter" [2018] International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting · EID: 2-s2.0-85060127219 | |
"Evaluation of organic rankine cycles in an air-brayton combined cycle for microreactor applications" [2018] International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting · EID: 2-s2.0-85060154081 | |
"In situ tensile study of PM-HIP and wrought 316 L stainless steel and Inconel 625 alloys with high energy diffraction microscopy" Darren C. Pagan, Elizabeth M. Getto, Janelle P. Wharry, Donna Post Guillen, [2018] Materials Science and Engineering A · DOI: 10.1016/j.msea.2018.09.083 · EID: 2-s2.0-85054434582 | |
"Response surface data for sensitivity study of industrial spray injected fluidized bed reactor" Donna P. Guillen, Alexander W. Abboud, [2018] Data in Brief · DOI: 10.1016/j.dib.2018.09.105 · EID: 2-s2.0-85054651050 | |
"Sensitivity study of a full-scale industrial spray-injected fluidized bed reactor" Donna P. Guillen, Alexander W. Abboud, [2018] Powder Technology · DOI: 10.1016/j.powtec.2018.04.065 · EID: 2-s2.0-85046481543 | |
"Validation hierarchy for waste vitrification models" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85063009616 | |
"Decision-support for Digester-Algae IntegRation for Improved Environmental and Economic Sustainability (DAIRIEES)" Donna Post Guillen, [2017] · DOI: 10.2172/1389180 | |
"Neutron irradiation of nuclear structural materials fabricated by powder metallurgy with hot isostatic pressing" [2017] Transactions of the American Nuclear Society · EID: 2-s2.0-85033461907 | |
"X-ray tomography of feed-to-glass transition of simulated borosilicate waste glasses"
Donna P. Guillen, Jaroslav Klouzek, Richard Pokorny, Tetsuji Yano, SeungMin Lee, Michael J. Schweiger, Pavel Hrma, William H. Harris,
[2017]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.14895
· EID: 2-s2.0-85019022647
High‐level waste feed composition affects the overall melting rate by influencing the chemical, thermophysical, and morphological properties of a cold cap layer that floats on the molten glass where most feed‐to‐glass reactions occur. Data from X‐ray computed tomography imaging of melting pellets comprised of a simulated high‐aluminum feed reveal the morphology of bubbles, known as the primary foam, for various feed compositions at temperatures between 600°C and 1040°C. These feeds were formulated to make glasses with viscosities ranging from 0.5 to 9.5 Pa s at 1150°C, which was accomplished by changing the SiO2/(B2O3+Na2O+Li2O) ratio in the final glass. Pellet dimensions and profile area, average and maximum bubble areas, bubble diameter, and void fraction were evaluated. The feed viscosity strongly affects the onset of the primary foaming and the foam collapse temperature. Despite the decreasing amount of gas‐evolving components (Li2CO3, H3BO3, and Na2CO3), as the feed viscosity increases, the measured foam expansion rate does not decrease. This suggests that the primary foaming is not only affected by changes in the primary melt viscosity but also by the compositional reaction kinetic effects. The temperature‐dependent foam morphological data will be used to inform cold cap model development for a high‐level radioactive waste glass melter. |
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"Cold Cap Bubble Topology" Lisa E. Mitchell, Donna Post Guillen, [2016] · DOI: 10.2172/1490045 | |
"Computational fluid dynamics modeling of bubbling in a viscous fluid for validation of waste glass melter modeling" [2016] International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 · EID: 2-s2.0-84992051595 | |
"Computational fluid dynamics simulation of a pilot-scale waste glass melter" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85033211920 | |
"Energy technology 2015: Carbon dioxide management and other technologies" [2016] Energy Technology 2015: Carbon Dioxide Management and Other Technologies · DOI: 10.1007/978-3-319-48220-0 · EID: 2-s2.0-85028801285 | |
"Energy technology 2016: Carbon dioxide management and other technologies" [2016] Energy Technology 2016: Carbon Dioxide Management and Other Technologies · DOI: 10.1007/978-3-319-48182-1 · EID: 2-s2.0-85028892135 | |
"Framework and algorithms for illustrative visualizations of time-varying flows on unstructured meshes" Donna Post Guillen, Alark Joshi, Srinivas Garimella, Alexander S. Rattner, [2016] Advances in Engineering Software · DOI: 10.1016/j.advengsoft.2016.02.004 · EID: 2-s2.0-84960969045 | |
"Reduction of GHG emissions through the conversion of dairy waste to value-added materials and products" Chaston Ellis, Donna Post Guillen, Kevin Feris, Erik R. Coats, Armando McDonald, Caryn Wendt, [2016] Energy Technology 2016: Carbon Dioxide Management and Other Technologies · DOI: 10.1007/978-3-319-48182-1_13 · EID: 2-s2.0-85028817538 | |
"Three-dimensional FIB/EBSD characterization of irradiated HfAl |
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"Foreword special issue on the international topical meeting on advances in thermal hydraulics (Ath'14)" [2015] Nuclear Technology · EID: 2-s2.0-84937956244 | |
"Modeling the vitrification of hanford tank waste" [2015] Transactions of the American Nuclear Society · EID: 2-s2.0-84988842008 | |
"One-Dimensional Cold Cap Model for Melters with Bubblers"
Zachary J. Hilliard, Derek R. Dixon, Michael J. Schweiger, Donna P. Guillen, Albert A. Kruger, Pavel Hrma, Richard Pokorny,
[2015]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.13775
· EID: 2-s2.0-84943365669
The rate of glass production during vitrification in an all‐electrical melter greatly impacts the cost and schedule of nuclear waste treatment and immobilization. The feed is charged to the melter on the top of the molten glass, where it forms a layer of reacting and melting material, called the cold cap. During the final stages of the batch‐to‐glass conversion process, gases evolved from reactions produce primary foam, the growth and collapse of which controls the glass production rate. The mathematical model of the cold cap was revised to include functional representation of primary foam behavior and to account for the dry cold cap surface. The melting rate is computed as a response to the dependence of the primary foam collapse temperature on the heating rate and melter operating conditions, including the effect of bubbling on the cold cap bottom and top surface temperatures. The simulation results are in good agreement with experimental data from laboratory‐scale and pilot‐scale melter studies. The cold cap model will become part of the full three‐dimensional mathematical model of the waste glass melter. |
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"Thermal evaluation of alternate shipping cask for irradiated experiments" Donna Post Guillen, [2015] Nuclear Technology · DOI: 10.13182/nt14-62 · EID: 2-s2.0-84937904547 | |
"Foreword" [2014] Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting · EID: 2-s2.0-84908223392 | |
"High conduction neutron absorber to simulate fast reactor environment in an existing test reactor" Larry R. Greenwood, James R. Parry, Donna Post Guillen, [2014] Journal of Radioanalytical and Nuclear Chemistry · DOI: 10.1007/s10967-014-3251-6 · EID: 2-s2.0-84939887729 | |
"Thermal evaluation of alternate shipping cask for GTRI experiments" [2014] Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting · EID: 2-s2.0-84908231017 | |
"Thermal predictions of the cooling of waste glass canisters" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84939163204 | |
"Extensible framework for illustrative visualization of time-varying flows" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902478985 | |
"Effect of Materials on the Autoignition of Cyclopentane" Donna Post Guillen, [2012] Energy Technology 2012: Carbon Dioxide Management and Other Technologies · DOI: 10.1002/9781118365038.ch19 · EID: 2-s2.0-84886359854 | |
"Energy Technology 2012: Carbon Dioxide Management and Other Technologies" [2012] Energy Technology 2012: Carbon Dioxide Management and Other Technologies · DOI: 10.1002/9781118365038 · EID: 2-s2.0-84891585286 | |
"TMS Annual Meeting: Preface" [2012] TMS Annual Meeting · EID: 2-s2.0-84860811310 | |
"The autoignition of cyclopentane in an ignition quality tester" Donna Post Guillen, [2012] JOM · DOI: 10.1007/s11837-012-0369-2 · EID: 2-s2.0-84865212113 | |
"Thermal evaluation of uranium silicide miniplates irradiated at high heat flux" Donna Post Guillen, [2012] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2012.06.010 · EID: 2-s2.0-84864474012 | |
"Waste heat recovery from the advanced test reactor secondary coolant loop" [2012] Advances in Thermal Hydraulics 2012, ATH 2012 · EID: 2-s2.0-84880496572 | |
"Development of a Direct Evaporator for the Organic Rankine Cycle" Helge Klockow, Matthew Lehar, Sebastian Freund, Jennifer Jackson, Donna Guillen, [2011] Energy Technology 2011: Carbon Dioxide and Other Greenhouse Gas Reduction Metallurgy and Waste Heat Recovery · DOI: 10.1002/9781118061886.ch3 · EID: 2-s2.0-84885962509 | |
"Development of a computational multiphase flow model for Fischer Tropsch synthesis in a slurry bubble column reactor" Tami Grimmett, Anastasia M. Gandrik, Steven P. Antal, Donna Post Guillen, [2011] Chemical Engineering Journal · DOI: 10.1016/j.cej.2011.08.078 · EID: 2-s2.0-81555228704 | |
"Integrated static and flow-through capsule assembly for irradiation testing" [2011] Transactions of the American Nuclear Society · EID: 2-s2.0-84875664882 | |
"Thermal stability of cyclopentane as an organic Rankine cycle working fluid" Lucia M. Petkovic, Donna Post Guillen, Daniel M. Ginosar, [2011] Energy and Fuels · DOI: 10.1021/ef200639r · EID: 2-s2.0-80052902493 | |
"Fabrication and characterization of a conduction cooled thermal neutron filter" [2010] International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 · EID: 2-s2.0-77956220458 | |
"In-pile experiment of a new hafnium aluminide composite material to enable fast neutron testing in the Advanced Test Reactor" [2010] International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 · EID: 2-s2.0-77956203291 | |
"Progress towards modeling of fischer tropsch synthesis in a slurry bubble column reactor" [2010] AIChE Annual Meeting, Conference Proceedings · EID: 2-s2.0-78751540920 | |
"Development and validation of a multifield model of churn-turbulent gas/liquid flows"
Steven P. Antal, Michael Z. Podowski, Donna Post Guillen, Matthias Beyer, Dirk Lucas, Elena A. Tselishcheva,
[2009]
International Conference on Nuclear Engineering, Proceedings, ICONE
· DOI: 10.1115/icone17-75210
· EID: 2-s2.0-77952938449
The accuracy of numerical predictions for gas/liquid two-phase flows using Computational Multiphase Fluid Dynamics (CMFD) methods strongly depends on the formulation of models governing the interaction between the continuous liquid field and bubbles of different sizes. The purpose of this paper is to develop, test and validate a multifield model of adiabatic gas/liquid flows at intermediate gas concentrations (e.g., churn-turbulent flow regime), in which multiple-size bubbles are divided into a specified number of groups, each representing a prescribed range of sizes. The proposed modeling concept uses transport equations for the continuous liquid field and for each bubble field. The overall model has been implemented in the NPHASE-CMFD computer code. The results of NPHASE-CMFD simulations have been validated against the experimental data from the TOPFLOW test facility. Also, a parametric analysis on the effect of various modeling assumptions has been performed. |
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"Optimization of a two-fluid hydrodynamic model of churn-turbulent flows"
Jonathan K. Shelley, Steven P. Antal, Elena A. Tselishcheva, Michael Z. Podowski, Dirk Lucas, Matthias Beyer, Donna Post Guillen,
[2009]
International Conference on Nuclear Engineering, Proceedings, ICONE
· DOI: 10.1115/icone17-75113
· EID: 2-s2.0-77952920948
A hydrodynamic model of two-phase, churn-turbulent flows is being developed using the computational multiphase fluid dynamics (CMFD) code, NPHASE-CMFD. The numerical solutions obtained by this model are compared with experimental data obtained at the TOPFLOW facility of the Institute of Safety Research at the Forschungszentrum Dresden-Rossendorf. The TOPFLOW data is a high quality experimental database of upward, co-current air-water flows in a vertical pipe suitable for validation of computational fluid dynamics (CFD) codes. A five-field CMFD model was developed for the continuous liquid phase and four bubble size groups using mechanistic closure models for the ensemble-averaged Navier-Stokes equations. Mechanistic models for the drag and non-drag interfacial forces are implemented to include the governing physics to describe the hydrodynamic forces controlling the gas distribution. The closure models provide the functional form of the interfacial forces, with user defined coefficients to adjust the force magnitude. An optimization strategy was devised for these coefficients using commercial design optimization software. This paper demonstrates an approach to optimizing CMFD model parameters using a design optimization approach. Computed radial void fraction profiles predicted by the NPHASE-CMFD code are compared to experimental data for four bubble size groups. |
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"Development of an experiment process for the advanced test reactor" [2008] Transactions of the American Nuclear Society · EID: 2-s2.0-55249115328 | |
"Incorporation of reaction kinetics into a multiphase, hydrodynamic model of a Fischer Tropsch slurry bubble column reactor" [2008] AIChE Annual Meeting, Conference Proceedings · EID: 2-s2.0-79952300133 | |
"Kinetic modeling of a fischer-tropsch reaction over a cobalt catalyst in a slurry bubble column reactor for incorporation into a computational multipiiase fluid dynamics model" [2008] 25th Annual International Pittsburgh Coal Conference, PCC - Proceedings · EID: 2-s2.0-70349595915 | |
"Thermal hydraulic effect of fuel plate surface roughness" Timothy S. Yoder, Donna Post Guillen, [2008] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2008.03.014 · EID: 2-s2.0-48149109778 | |
"Thermal performance of a fast neutron test concept for the advanced test reactor" [2008] Transactions of the American Nuclear Society · EID: 2-s2.0-55249087176 | |
"NPHASE predictions of turbulent flow in the lower plenum of a prismatic gas-cooled reactor" [2007] Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 · EID: 2-s2.0-80053170818 | |
"Preliminary study of turbulent flow in the lower plenum of a gas-cooled reactor" [2007] Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 · EID: 2-s2.0-80053171186 | |
"Review of experimental capabilities and hydrodynamic data for validation of CFD based predictions for slurry bubble column reactors" [2007] 2007 AIChE Annual Meeting · EID: 2-s2.0-58049108873 | |
"Streamlining of the RELAP5-3D code" [2007] Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 · EID: 2-s2.0-80053171720 | |
"Computational flow predictions for the lower plenum of a high-temperature, gas-cooled reactor" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33845537470 | |
"Effect of grit-blasting on substrate roughness and coating adhesion" Donna Post Guillen, Douglas M. Deason, William Rhodaberger, Elliott Sampson, Dominic J. Varacalle, [2006] Journal of Thermal Spray Technology · DOI: 10.1361/105996306x124347 · EID: 2-s2.0-33748885768 | |
"Estimation of critical flow velocity for collapse of gas test loop booster fuel assembly"
Mark J. Russell, Donna Post Guillen,
[2006]
International Conference on Nuclear Engineering, Proceedings, ICONE
· DOI: 10.1115/icone14-89130
· EID: 2-s2.0-33845800233
This paper presents calculations performed to determine the critical flow velocity for plate collapse due to static instability for the Gas Test Loop booster fuel assembly. Long, slender plates arranged in a parallel configuration can experience static divergence and collapse at sufficiently high coolant flow rates. Such collapse was exhibited by the Oak Ridge High Flux Reactor in the 1940s and the Engineering Test Reactor at the Idaho National Laboratory in the 1950s. Theoretical formulas outlined by Miller, based upon wide-beam theory and Bernoulli’s equation, were used for the analysis. Calculations based upon Miller’s theory show that the actual coolant flow velocity is only 6% of the predicted critical flow velocity. Since there is a considerable margin between the theoretically predicted plate collapse velocity and the design velocity, the phenomena of plate collapse due to static instability is unlikely. |
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"In-flight oxidation of aluminum in the twin-wire electric arc process" Brian G. Williams, Donna Post Guillen, [2006] Journal of Thermal Spray Technology · DOI: 10.1361/105996306x92604 · EID: 2-s2.0-33645641288 | |
"Process control systems in the chemical industry: Safety vs. security"
Donna Post Guillen, Thomas Anderson, Jeffrey Hahn,
[2006]
Process Safety Progress
· DOI: 10.1002/prs.10114
· EID: 2-s2.0-33845713129
Traditionally, the primary focus of the chemical industry has been safety and productivity. However, recent threats to our nation's critical infrastructure have prompted a tightening of security measures across many different industry sectors. Reducing control system vulnerabilities against physical and cyber attack is necessary to ensure the safety, reliability, integrity, and availability of these systems. The U.S. Department of Homeland Security has developed a strategy to secure these vulnerabilities. Crucial to this strategy is the Control Systems Security and Test Center (CSSTC) established to test and analyze control systems and their components. In addition, the CSSTC promotes a proactive, collaborative approach to increase industry's awareness of standards, products, and processes that can enhance the security of control systems. This paper outlines measures that can be taken to enhance the cybersecurity of process control systems in the chemical sector. © 2005 American Institute of Chemical Engineers Process Saf Prog, 2006 |
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"Restructuring RELAP5-3D for next generation nuclear plant analysis" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33746073338 | |
"Specification of surface roughness for hydraulic flow test plates" [2006] Surface Engineering - Proceedings of the 5th International Surface Engineering Conference · EID: 2-s2.0-33846126609 | |
"Process control systems in the chemical industry: Safely vs. Security" [2005] AIChE Spring Meeting 2005 - 20th International Conference of CCPS - Center for Chemical Process Safety 2005 · EID: 2-s2.0-33645008588 | |
"Thermal hydraulic analysis of a gas test loop system" [2005] Transactions of the American Nuclear Society · EID: 2-s2.0-33244473745 | |
"A survey of department of energy-sponsored geophysical research for shallow waste site characterization" R. C. Hertzog, D. P. Guillen, [2004] Vadose Zone Journal · DOI: 10.2113/3.1.122 · EID: 2-s2.0-51449112206 | |
"Aerothermodynamics of the Mars rover and sample return lander" [1992] Advances in the Astronautical Sciences · EID: 2-s2.0-0026630846 | |
"CFD application to flexible aerobrake design for Mars entry" [1992] Advances in the Astronautical Sciences · EID: 2-s2.0-0026698488 | |
Source: ORCID/CrossRef using DOI |
This NSUF Profile is 70
Authored 10+ NSUF-supported publications
Presented an NSUF-supported publication
Submitted an RTE Proposal to NSUF
Awarded 3+ RTE Proposals
Collaborated on an RTE Proposal
Reviewed 10+ RTE Proposals
Understanding the Origin of Irradiation-Induced Yield Drop Phenomena in Grade 91 - FY 2023 RTE 2nd Call, #23-4703
Microstructural Examination of Irradiation Effects on Metal Matrix Composite Neutron Absorber - FY 2021 RTE 1st Call, #21-4280
Beamline Examination of a Hf-Al Metal-Matrix Composite Material - FY 2016 CINR, #16-CINR-639
Microstructural Examination of Neutron Irradiated Al-HfAl3 Metal Matrix Composite Materials for Application to Neutron Spectrum Modification in Nuclear Reactors - FY 2017 RTE 3rd Call, #17-1028
Irradiation Effect on Thermophysical Properties of Hf3Al-Al Composite: A Concept for Fast Neutron Testing at ATR - FY 2009 Fall Solicitation for User Proposals, #09-157
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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