Skip Navigation LinksFY17_RandD_Awards

​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​FY 2017 Research and Development Awards

DOE is awarding over $31 million through its Nuclear Energy University Program (NEUP) to support 32 university-led nuclear energy research and development projects in 23 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their student’s opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

NEUP 2017 R&D Award Abstracts
  
  
  
  
  
  
  
Description
  
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/2017_CFA_Technical_Abstract_17-12628.pdf
17
California State University, East BayResearch and DevelopmentFuel Cycle Research and Development$785,714
Mineral impurities are common in bentonite and clay buffer materials, proposed for many nuclear waste disposal options. Researchers will investigate the effects of calcite impurities on uranium(VI) sorption onto montmorillonite before and after mineral exposure to heat. Based on experimental sorption data and EXAFS analysis we will develop a new surface complexation model to determine under which conditions impurity effects are relevant, and how they can be incorporated in performance assessment models.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12798_TechnicalAbstract_2017CFATechnicalAbstract17-12798.pdf
17
Clemson UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop a ceramic membrane technology for tritium separation and recovery to support the nuclear fuel cycle. Low-temperature water adsorption properties of nanoscale structured ceramics, combined with demonstrated hydrogen isotope exchange in their hydrated layers provide a low cost and unique avenue to address tritium management challenges.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/2017_CFA_Technical_Abstract_12609.pdf
17
Colorado School of MinesResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will improve the production of ferritic/martensitic steels to suppress void swelling, embrittlement and improve low temperature ductility loss through reduction of ‘free’ nitrogen in the alloy. The process will simultaneously create a fine precipitate dispersion that refines the microstructure and increases microstructural stability with temperature and irradiation exposure.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/2017_CFA_Technical_Abstract_12647.pdf
17
Massachusetts Institute of TechnologyResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will characterize the thermal-hydraulics behavior of accident tolerant fuel (ATF) materials by measuring critical heat flux (CHF) under normal and off-normal light water reactor conditions, and Leidenfrost temperature in post-loss-of-coolant accident (LOCA) conditions. This work will yield material-specific models and/or correlations that can be readily implemented in state-of-the-art simulation tools.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13011_TechnicalAbstract_2017CFATechnicalAbstract13011.pdf
17
Missouri University of Science and TechnologyResearch and DevelopmentFuel Cycle Research and Development$799,317
Researchers will design, build, test and install a submersible tomography platform for performing pool-side physical, structural, and chemical characterization of irradiated fuel elements for test reactors.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12496_TechnicalAbstract_2017CFATechnicalAbstractCFA-17-12496.pdf
17
Texas A&M UniversityResearch and DevelopmentFuel Cycle Research and Development$399,857
Researchers will explore bulk removal of U, Np, Pu and Am, from used nuclear fuel by studying the mechanisms of removal. A co-crystallization of the hexavalent actinides with U(VI) has already been demonstrated and researchers plan to develop a process based around this approach. Removal of these elements would be advantageous for future nuclear fuel recycle.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/2017_CFA_Technical_Abstract_12824.pdf
17
University of California, BerkeleyResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop better modeling methods, detectors, and facility design approaches to enable detection of inadvertent and deliberate hold up of fissile material in reprocessing and other nuclear material bulk handling facilities. The team will integrate results from this research project into a design methodology for future facilities to ensure accurate and reliable process monitoring for sustainable operation.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12782_TechnicalAbstract_2017CFATechnicalAbstract17-12782.pdf
17
University of California, IrvineResearch and DevelopmentFuel Cycle Research and Development$800,000
This project will investigate the alpha and gamma radiolysis-induced chemical degradation of ligands used for the removal of minor actinides from used nuclear fuel in advanced extraction systems such as ALSEP. Researchers will emphasize organic phase degradation, particularly complex solvents with multiple ligands as well as metal loaded solvents. The project will improve predictive capabilities of extraction processes by elucidating degradation pathways.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12757_TechnicalAbstract_2017CFATechnicalAbstract12757.pdf
17
University of IdahoResearch and DevelopmentFuel Cycle Research and Development$796,741
This project will evaluate the electrochemical speciation behavior of iodide, and telluride in LiCl-KCl eutectic, LiCl, and LiCl + Li2O electrolytes at temperatures relevant to reprocessing conditions. By using rhenium as surrogate for technetium, the electrochemical, and chemical speciation properties of rhenium ions will be investigated in chloride molten salts with the addition of molybdenum and ruthenium.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12701_TechnicalAbstract_2017CFATechnicalAbstract-17-12701.pdf
17
University of Nevada, RenoResearch and DevelopmentFuel Cycle Research and Development$400,000
Researchers will develop physics-based computational tools to predict used nuclear fuel cladding temperatures within, and water vapor removal rates from, canisters during existing and proposed drying processes. The project will explore a range of gas pressures (including rarefication), and steady and unsteady external gas flows rates. The tools will be used to develop drying processes that minimize drying time while maintaining cladding temperatures.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12688_TechnicalAbstract_2017CFATechnicalAbstract17-12688.pdf
17
University of New MexicoResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop a holistic best estimate assessment of the potential impact of different ATF cladding materials with regards to heat transfer characteristics, the boiling curve, critical heat flux, fuel mass/volume/specific power density, and neutronics effects due to changes in the lattice design or parasitic neutron absorption during design basis accident conditions in light water reactors.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13131_TechnicalAbstract_2017CFAAbstract17-13131.pdf
17
University of New MexicoResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop extreme performance bulk nanocomposite Zirconium/Niobium and Copper/Niobium alloys with varying layer thickness that can withstand irradiation doses up to 600 dpa at elevated temperatures (up to 700°C) using innovative accumulative roll bonding techniques. Ion irradiations are proposed to test the performance of the alloys at elevated temperatures.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12996_TechnicalAbstract_2017CFATechnicalAbstract17-12996.pdf
17
University of South CarolinaResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop detection systems capable of neutron, gamma-ray, x-ray, and alpha monitoring in high-temperature and high radiation environments for extended periods of time. The detectors will be used to strengthen nuclear safeguards by enhancing nuclear material control and accounting in nuclear fuel reprocessing facilities.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13125_TechnicalAbstract_2017CFASummaryAbstractRPA-17-13125.pdf
17
University of Tennessee at KnoxvilleResearch and DevelopmentFuel Cycle Research and Development$800,000
This projects will study the thermodynamics of melt and quench phases of nuclear waste glasses and glass ceramics and link this information to the underlying short-range and medium-range structure. Advanced calorimetric techniques and neutron total scattering with pair distribution function analysis will be applied to obtain these data. Computer simulations will complement the experimental effort.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12886_TechnicalAbstract_2017CFATechnicalAbstractCFA-17-12886.pdf
17
University of VirginiaResearch and DevelopmentFuel Cycle Research and Development$799,000
Researchers will determine the root cause of corrosion within Kr-85 storage canisters in order to better understand current corrosion rates. The project will focus on expanding available research on Rb corrosion interactions and other contributing factors to better understand the corrosion phenomenon in current steel canisters.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12463_TechnicalAbstract_2017CFATechnicalAbstract17-12463.pdf
17
University of Wisconsin-MadisonResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will develop extreme performance high entropy alloys (HEAs) as for new metal alloy cladding for fast reactor applications. Two very promising, single solution BCC HEAs will be investigated. The project will deliver an extensive irradiation resistance study of a new promising yet unexplored cladding concept.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12549_TechnicalAbstract_2017CFATechnicalAbstract17-12549.pdf
17
University of Wisconsin-MadisonResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will study critical heat flux (CHF) behavior focused on innovative accident tolerant fuel (ATF) cladding. The project includes separate effects screening tests to measure CHF for various ATF clad materials and surface characteristics with measurements of surface wettability. Pressurized flow boiling experiments will simulate prototypical reactor conditions for evaluating the best ATF clad materials coupled with CHF modeling.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13019_TechnicalAbstract_2017CFATechnicalAbstract17-13019.pdf
17
Virginia Commonwealth UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will perform separate-effects and system-wide tests of the AREVA and GE accident tolerant fuel concepts currently under consideration. The project will investigate the impact of cladding surface characteristics in critical heat flux (CHF) under normal and anticipated off-normal conditions. The experimental results will be used to develop and validate enhanced models for the prediction of CHF and will be implemented in various subchannel and system analysis codes.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13054_TechnicalAbstract_2017CFATechnicalAbstract17-13054.pdf
17
Washington State UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000
Researchers will study the effects of simulated used nuclear fuel (UNF) chemistry and microstructure on its dissolution in geologic repository conditions. The results will advance models for UNF evolution in repository conditions, enabling reliable prediction of degradation and long-term performance of used nuclear fuel for up to one million years.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12506_TechnicalAbstract_2017CFATechnicalAbstract12506.pdf
17
University of FloridaResearch and DevelopmentMission Supporting Nuclear Energy: Integral Benchmark Evaluations$398,265
Researchers will perform reactor physics benchmark evaluations of Power Burst Facility experiments regarding differential reactivity worth of the control and transient rods, shim rod worth, in-pile-tube reactivity worth, shutdown reactivity, fuel assembly reactivity worth, core void coefficients of reactivity, in-pile-tube void coefficient, and coolant temperature coefficient of reactivity. The results will be incorporated in the International Reactor Physics Experiment Evaluation Project (IRPhEP).
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12748_TechnicalAbstract_2017CFATechnicalAbstract12748.pdf
17
Oregon State UniversityResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$800,000
Researchers will enhance MARMOT to predict mechanical and corrosion properties of dual-phase stainless steels as a function of composition, aging time and temperature by using combined experimental data and lower length scale models.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12555_TechnicalAbstract_2017CFATechnicalAbstract12555.pdf
17
Rensselaer Polytechnic InstituteResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$800,000
Researchers will provide end users an ability to run both MCNP6 and PROTEUS codes from a common user input in Workbench by (1) templating user-provided engineering scale specifications to code-specific input requirements, (2) enabling multi-fidelity analysis of a system from a common input using MCNP6 and PROTEUS and (3) allowing the easy use of high-fidelity simulations to inform lower-order models for the design, analysis, and licensing of advanced nuclear systems and experiments.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12939_TechnicalAbstract_2017CFATechnicalAbstractRPA17-12939.pdf
17
University of New HampshireResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$800,000
Researchers will expand the capabilities of BISON and MOOSE to simulate the structural dynamic response of fuel rods and fuel assemblies during handling (wet and dry storage) and transportation. Expanding the capabilities of BISON and MOOSE to facilitate the evaluation of the dynamic response of fuel rods and assemblies is important to conduct a more reliable risk assessment of fuel assemblies, as well as storage and transportation casks.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13179_TechnicalAbstract_2017CFATechnicalAbstract13179.pdf
17
University of OklahomaResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$786,648
Researchers will implement and validate state-of-the-art turbulence modeling techniques in Nek5000 to improve predition of liquid metal flows. Specific methods to be investigated include: variable PrT and algebraic heat flux models (AHFM) for URANS simulation; partially-averaged Navier-Stokes (PANS) and dynamic hybrid RANS-LES (DHRL) for hybrid RANS-LES simulation; and variable PrT subgrid heat flux modeling for LES.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12848_TechnicalAbstract_2017CFATechnicalAbstractRPA-17-12848.pdf
17
Purdue UniversityResearch and DevelopmentNuclear Energy: Cybersecurity$800,000
Researchers will develop a first-of-a-kind physics-based defense-in-depth strategy to defend against false data injection attacks which attempt to change the information used by the I/C network to set reactor state. The approach employs a new design philosophy to check for information trustworthiness/integrity in order to determine whether the information is genuinely generated during the actual operation of the nuclear unit under either normal or off-normal conditions.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12538_TechnicalAbstract_2017CFATechnicalAbstract12538.pdf
17
Kansas State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will investigate the role of raw water on degraded heat transfer and fluid flow in the reactor core and debris bed. X-ray imaging techniques, optical-fiber high speed temperature sensing systems and radioactive tracer salts will be used to simultaneously measure experimental data on void fraction, temperature and salt deposition rate. This data will be used to obtain correlations for heat transfer and fluid flow in case of raw water injection.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12502_TechnicalAbstract_2017CFATechnicalAbstract17-12502.pdf
17
Texas A&M UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will produce high-quality, high spatial and temporal resolution temperature and flow datasets for wire-wrapped rod bundle geometries. Different bundle sizes, configurations (including duct's and pin's deformation) and Low-Prandlt fluids will be investigated. A unique set of data will be produced to support advanced CFD tools validation, including Nek5000.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12723_TechnicalAbstract_2017CFATechnicalAbstractRPA-17-12723.pdf
17
The Ohio State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,985
Researchers will develop a computationally feasible and user friendly process to augment the traditional probabilistic risk assessment (PRA) results with improved representation of epistemic uncertainties and process/hardware/software/human interactions at plant level applications.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12664_TechnicalAbstract_2017CFATechnicalAbstract12664.pdf
17
University of California, BerkeleyResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will develop a methodology for the design of molten salt reactor (MSR) Separate Effect Test and Integral Effect Test experiments. This methodology will identify and quantify sources of scaling distortion including radiative heat transport. The project would improve code performance and assist FHR/MSR vendors who are making licensing applications based on code results.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12710_TechnicalAbstract_2017CFATechnicalAbstract17-12710.pdf
17
University of Central FloridaResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,999
Researchers will measure the diffusivities of non- radioactive isotopes of Kr, I, Cs, Sr, Ru and Ag in graphite and uncover the mechanisms of transport at temperatures between 600 – 1800 C using microstructural examinations and large scale computer simulations. By using a suite of experimental techniques and multiscale simulations, pertinent transport/retention mechanisms of fission products in the selected graphite grades will become evident.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12523_TechnicalAbstract_2017CFATechnicalAbstract12523.pdf
17
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will use advanced microanalytical analysis techniques to study SCC and IASCC of stainless steel and Ni-Cr alloy weldments. CERT, autoclave immersion, and ion irradiation will be used to determine synergistic effect of LWR environmental factors. Results from the experimental component of the proposed work scope will be used for enhanced predictive capability of the INL Grizzly code via XFEM.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12614_TechnicalAbstract_2017CFATechnicalAbstract12614.pdf
17
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,998
Researchers will develop a systematic Enterprise Risk Management framework, which utilizes Decision Tree (DT) logic to consider high-level production-loss scenarios, and their underlying physical and social causes throughout the lifecycle. In the proposed DT, uncertainty nodes will be quantified by plant-specific risk analysis using the Risk-Informed Safety Margin Characterization (RISMC) Toolkit, and cost-benefit analysis will be conducted for end states reflecting consequences of managerial decision-making.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12972_TechnicalAbstract_2017CFATechnicalAbstract12972.pdf
17
University of Massachusetts, LowellResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$400,000
Researchers will combine fluoride-salt-cooled, high temperature reactors (FHR) with advanced gas reactor (AGR) refueling technology to address several significant challenges that remain in the development of FHR technology. The project will adapt AGR refueling technology by using the new fuel-inside-radial-moderator fuel form, which will also introduce new ways of dealing with decay heat.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13115_TechnicalAbstract_2017CFATechnicalAbstract13115.pdf
17
University of MichiganResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will examine the effects of coolant leakage and air ingress through three different investigations. The overall objective of this work is to characterize near and far field behavior of Helium/Air mixing in containment, and to determine rates and amounts of air leaked back into the reactor after a depressurization event.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12830_TechnicalAbstract_2017CFATechnicalAbstract17-12830.pdf
17
University of Missouri, ColumbiaResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will use a variety of experimental techniques to acquire data for fission product diffusion, transport and adsorption of fission products in various graphites, relating to nuclear reactors at high temperatures. Measurements will be taken using non-irradiated graphite using fission product surrogates.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13020_TechnicalAbstract_2017CFATechnicalAbstract17-13020.pdf
17
University of New MexicoResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will develop a new bimetallic alloy (Incoloy 800H/Ni-201) structural material for the MSR, and compare its post-exposure mechanical performance in flowing FLiBe with single alloys SS 316, Hastelloy N, and Incoloy 800H, in the context of ASME codification.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12678_TechnicalAbstract_2017CFATechnicalAbstract-17-12678.pdf
17
University of South CarolinaResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will develop NDE sensors and probabilistic cable insulation diagnosis and prognosis algorithms (particle filtering), and modeling and experiments to monitor cable insulation health. Two different types of sensor will be deployed to detect insulation damage. The team will also develop cable insulation degradation modeling to further understand defects in cable insulation.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13080_TechnicalAbstract_2017CFATechnicalAbstract17-13080.pdf
17
University of VirginiaResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will study the long-term degradation mechanisms of SiC/SiC composites in helium coolant environments by slow crack growth (SCG). This will be achieved through multiscale testing in hot, O2-contaminated He and evaluation of the effect of SCG on hermeticity during in situ testing. Results will be extended to predictive low-level and component-scale SCG models and integrated into the development of ASME standards for use of SiC/SiC in nuclear reactors.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12481_TechnicalAbstract_2017CFATechnicalAbstract17-12481.pdf
17
University of Wisconsin-MadisonResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$400,000
Researchers will develop an advanced supercritical Brayton power cycle directly coupled to a fission reactor. The project will carry out a comprehensive optimization of the cycle operating conditions, working fluid, and configuration; develop detailed designs of each subcomponent; and demonstrate/develop critical technologies such as turbomachinery seals and bearings, reactor material corrosion and strength demonstrations, and supercritical heat transfer.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-13232_TechnicalAbstract_2017CFATechnicalAbstract17-13232.pdf
17
University of Wisconsin-MadisonResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
The goal of the proposed research is to experimentally investigate radiation heat transport in molten salts, and to add functionality for radiative heat transport in a thermal-hydraulics system code. This includes obtaining highly resolved measurements of the optical absorption and emissivity of liquid salts.
  
https://neup.inl.gov/SiteAssets/FY%202017%20Abstracts/CFA-17-12547_TechnicalAbstract_2017CFATechnicalAbstract17-12547.pdf
17
Virginia Polytechnic Institute and State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,697
Researchers will foster the development of collaborative and intelligent technology that support adaptive/unplanned decision making during an outage, thereby reducing undesirable events arising from deficient coordination, communication, judgment or documentation. This research will involve concurrent research efforts on function analysis, natural language processing, scheduling and novel visualizations.


*Actual project funding will be established during the award negotiation phase.​