- Donna Guillen
- Idaho National Laboratory
- Distinguished Research Engineer
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.
- beamline, Composites, heat transfer, Material Characterization, Mechanical Properties, Thermal Hydraulics, Validation of computational models
"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
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.
|"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 cast 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|
"Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material"
Donna Guillen, William Harris,
Metallurgical and Materials Transactions E
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.
|"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]|
This NSUF Profile is 55
Authored an NSUF-supported publication
Presented an NSUF-supported publication
Submitted an RTE Proposal to NSUF
Awarded an RTE Proposal
Collaborated on an RTE Proposal
Reviewed 10+ RTE Proposals
Irradiation Effect on Thermophysical Properties of Hf3Al-Al Composite: A Concept for Fast Neutron Testing at ATR - FY 2009 Fall Solicitation for User Proposals, #157
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, #1028