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Skip Navigation LinksFY24_CINR_R&D_ Awards

​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​FY 2024 Research and Development Awards

DOE is awarding more than $44 million through NEUP to support 25 university-led nuclear energy research and development projects in 22 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with 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.  

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Description
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31635_TechnicalAbstract_2024CFATechnicalAbstract24-31635.pdf
24
Purdue UniversityResearch and DevelopmentAdvanced Manufacturing Technologies$1,100,000
This project aims to understand how interparticle evolution during hot isostatic pressing (HIP) influences fracture toughness of Al-bearing steels. The team will use a series of interrupted HIP experiments with phase field models to understand the formation mechanisms of interparticle defects during HIP of alumina-forming austenitic (AFA) stainless steels and FeCrAl steels, and the influence of these defects on fracture behavior.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31909_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31909.pdf
24
University of Minnesota, Twin CitiesResearch and DevelopmentAdvanced Manufacturing Technologies$1,043,271
This project proposes to develop a predictive capability for processing-microstructure-property correlations in additive manufactured microstructures utilizing a multiscale approach encompassing bulk creep tests, miniaturized tensile testing, and a high-throughput, indentation based, cost-effective method for elevated temperature mechanical mapping of additively manufactured 316H Stainless Steel, Grade 91, and Titanium-Zirconium-Molybdenum (TZM) alloys.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31871_TechnicalAbstract_2024CFATechnicalAbstract24-31871.pdf
24
North Carolina State UniversityResearch and DevelopmentAdvanced Nuclear Materials$1,100,000
We propose a suite of fuel salt (FLiBe + U) infiltration experiments (University of Michigan – UM) followed by X-ray computed tomography, XCT (NCSU), in-situ mechanical property evaluation with scanning electron microscopy (NCSU) and high fidelity data analytics and modeling (NCSU/Leeds) along with complimentary porosimetry measurements (ORNL) and XPS analysis at University of Manchester (UoM). Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31912_TechnicalAbstract_2024CFATechnicalAbstract24-31912.pdf
24
North Carolina State UniversityResearch and DevelopmentAdvanced Nuclear Materials$1,100,000
The proposed goal is to leverage a blend of innovative molten salt corrosion experiments and cutting-edge characterization techniques to advance our understanding of molten salt corrosion in both commercial and additively manufactured (AM) stainless steel (SS) 316H, particularly under radiation or stress environments.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31715_TechnicalAbstract_2024CFATechnicalAbstract24-31715.pdf
24
University of Alabama at BirminghamResearch and DevelopmentAdvanced Nuclear Materials$1,100,000
This program is to use a polymer-derived ceramic approach to develop C-SiC/ZrC coatings on ZrO2 kernel substitute particles. We aim to create new fuel encapsulation materials in replacement of the coatings on fuel kernel particles, including the TRISO layers, for advanced reactors, conduct ion irradiation testing of the new materials for nuclear performance evaluation, and carry out detailed microstructure and composition characterization to assess the C-SiC/ZrC coated fuel particle behaviors.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31377_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31377.pdf
24
University of Nevada, RenoResearch and DevelopmentAdvanced Nuclear Materials$1,000,000
The project will focus on the development of materials and processes for regeneration and recycling of sorbents, and the transformation of iodine-loaded sorbents into waste forms. A combination of computational and experimental studies will be conducted to understand (a) how the components in a primary off-gas stream interact with the sorbent, (b) how this off-gas stream affects the regeneration lifetime, and (c) low-temperature binders and processing paths that leads to durable waste forms.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-32013_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-32013.pdf
24
University of MichiganResearch and DevelopmentConsent-based Siting for SNF Management$1,100,000
Through this project we seek to develop (1) guiding principles for respectful community engagement – to support consent-based siting – empirically rooted in the lived experiences of Native Communities; (2) metrics and indicators of consent; and (3) a generative AI tool to facilitate community-based storytelling of the past and imagining of the future to visualize how nuclear infrastructures have and could in the future alter community landscapes.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-32001_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-32001.pdf
24
Vanderbilt UniversityResearch and DevelopmentConsent-based Siting for SNF Management$1,000,000
We will use two phases of research to assist NE in understanding factors that influence the quality and extent of public engagement needed to address different people and communities seeking to make decisions regarding the siting of a CISF. Supporting NE’s the consent-based siting process we have developed an accelerated 2-year schedule, focusing on three geographic areas of the US: IL, TX & NM and the area served by the TVA/Duke Power —each contain multiple SNF storage facilities.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31312_TechnicalAbstract_2024CFATechnicalAbstract24-31312.pdf
24
University of Wisconsin-MadisonResearch and DevelopmentExisting Plant Optimization$1,100,000
This project will demonstrate that power uprates higher than the current state of operation can be reached using accident tolerant fuels in light water reactors while not exceeding reactor safety margins during normal operation and accidents. We will analyze it considering fuel enriched up to 10% and peak rod average burnup up to 75GWd/tU concerning reactor physics, thermal-hydraulics, reactor safety, and economics. Considerations will be made in consultation with the named industry advisory board.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31764_TechnicalAbstract_2024CFATechnicalAbstract31764.pdf
24
Massachusetts Institute of TechnologyResearch and DevelopmentFuels$1,000,000
Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31510_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31510.pdf
24
Oregon State UniversityResearch and DevelopmentFuels$1,000,000
The objective of this project is to enhance the safety and performance of light water reactors and other advanced reactor designs by gaining a fundamental understanding of fast gas reactor mechanisms and developing mechanistic models for UO2 and doped UO2 fuels under HBU and transient conditions.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31740_TechnicalAbstract_2024CFATechnicalAbstract24-31740.pdf
24
University of PittsburghResearch and DevelopmentFuels$1,000,000
We propose to develop a high-temperature nondestructive thermal conductivity (k) measurement system coupled with validated multiscale models to accurately determine the anisotropic thermal conductivity of SiC-SiC composite cladding tubes. The multiscale measurement and modeling results benefit both DOE ATF programs as well as providing a fundamental understanding of how the microstructure of the composite leads to its anisotropic properties.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31464_TechnicalAbstract_2024CFATechnicalAbstract24-31464.pdf
24
University of Wisconsin-MadisonResearch and DevelopmentFuels$1,000,000
The project will focus on investigating the impact of Cr-coating on the SiC-SiCf composite cladding of various architectures under normal operating and accident conditions in light water reactors and advanced reactors for the safe and economic deployment of SiC cladding. Cr-coating will provide protection from high-temperature corrosion and better hermeticity under accident conditions. The performance of the claddings will be evaluated through the corrosion test, reflood test, burst test, and non-destructive evaluation(NDE).
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31471_TechnicalAbstract_2024CFATechnicalAbstract-24-31471.pdf
24
University of Wisconsin-MadisonResearch and DevelopmentFuels$1,000,000
This project aims at developing a mechanistic understanding on the effects of Mo on α' precipitation and dislocation loop formation in FeCrAl alloys in thermal and irradiation conditions and turns it into a set of design principles guiding further optimization, by integrating atomistic simulations, CALPHAD modeling, thermal aging, proton irradiation, and advanced characterization. The material discoveries will be generalized to other solutes other than Mo.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31554_TechnicalAbstract_2024CFATechnicalAbstract31554.pdf
24
Massachusetts Institute of TechnologyResearch and DevelopmentLicensing, Safety, and Security$1,000,000
Reactor modelling relies on the detailed description of reactor systems but often lacks the true as-built characteristics of a system. This proposal seeks to fill these geometrical data gaps using available detector data, predictive models and machine learning in order to provide better information to analysis tools and thus better prediction of future performance.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31719_TechnicalAbstract_2024TechnicalAbstract24-31719.pdf
24
Rensselaer Polytechnic InstituteResearch and DevelopmentLicensing, Safety, and Security$1,000,000
The overarching goal of this project is to develop an innovative materials accounting and control technology by adopting an approach of “safeguard by design” during fuel fabrication to fill nuclear control technology gaps in tracing and tracking nuclear fuels for advanced nuclear reactors. The project is based on a concept of “taggants in fuels” that can greatly increase forensic attributes, and enhance intrinsic proliferation resistance and MPACT effectiveness for advanced nuclear fuel cycles.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31664_TechnicalAbstract_2024CFATechnicalAbstract24-31664.pdf
24
University of Illinois at Urbana-ChampaignResearch and DevelopmentLicensing, Safety, and Security$1,100,000
The objective of the proposed project is to develop and demonstrate a 3D boron-coated-straw detector array (3D-BCSDA) with high efficiency and spatial resolution. This detection system will be specifically designed to accurately assess the fissile mass in bulk nuclear material during pyroprocessing operations, thereby improving the precision and reliability of accountability measurements during separation.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31356_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31356.pdf
24
University of Maryland, College ParkResearch and DevelopmentLicensing, Safety, and Security$1,064,400
The overall objective of the proposed research is to improve the efficiency and usability of dynamic probabilistic risk assessment (PRA). Specifically, the first objective is to develop a new algorithm for dynamic PRA analysis that can significantly increase the computational efficiency. The second objective is to develop a question-answering system to streamline the process of risk-informed decision-making based on results obtained from the dynamic PRA analysis using the new algorithm.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31307_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31307.pdf
24
Virginia Commonwealth UniversityResearch and DevelopmentLicensing, Safety, and Security$1,100,000
The primary goal of this proposed project is to develop high fidelity Monte Carlo radiation transport models of a microcalorimetry detector informed by fuel depletion models of a molten salt reactor and a pebble bed reactor to quantify the current and future capabilities of this detector technology to characterize and assay used fuel from these reactors in near real-time.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31591_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31591.pdf
24
Boise State UniversityResearch and DevelopmentMeasuring, Monitoring, and Controls$1,100,000
The project goal is to develop a comprehensive guided-wave structural health monitoring system involving printed magnetostrictive ultrasonic transducers, wired data transmission, and an intuitive graphic user interface. In collaboration with the Ohio State University Research Reactor, we will evaluate the system’s effectiveness in high temperature and radiation environments.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31617_TechnicalAbstract_2024CFATechnicalAbstract24-31617.pdf
24
Brigham Young UniversityResearch and DevelopmentMeasuring, Monitoring, and Controls$1,099,924
We propose the development of an online monitoring instrument capable of quantifying heat transfer and salt composition for molten salt reactors (MSR). A dual electrochemistry/thermal conductivity probe (DETP) will be developed to measure the thermal properties and impurities within the salt simultaneously. The DETP will make use of a previously developed needle probe and electrodes for square-wave cyclic voltammetry measures of salt composition.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31544_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31544.pdf
24
Johns Hopkins UniversityResearch and DevelopmentMeasuring, Monitoring, and Controls$909,827
This project focuses on the transport of molten salt into nuclear graphite along with the investigation of ultrasonic methods for sensing graphite material property changes, especially elastic modulus, associated with intrusion of molten salt into the graphite microstructure. Experimental studies coupled with physics-based simulations will be used to assess strategies for in situ sensing of salt intrusion in the reactor environment to enhance long-term viability of molten salt reactors.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31840_TechnicalAbstract_2024CFATechnicalAbstract31840.pdf
24
Virginia Polytechnic Institute and State UniversityResearch and DevelopmentMeasuring, Monitoring, and Controls$1,000,000
In the proposed three-year program, the Center for Photonics Technology (CPT) at Virginia Tech will collaborate with Sentek Instrument (Sentek), Prysmian, and Idaho National Laboratory (INL) to develop and demonstrate a distributed acoustic emission (AE) sensing system for in-situ monitoring of ceramic fuel fracture.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31807_TechnicalAbstract_2024CFATechnicalAbstract24-31807.pdf
24
University of FloridaResearch and DevelopmentModeling and Simulation$999,999
The objective of this project is to develop a general capability for concurrent generation and use of physics-informed Gaussian process (GP)-based surrogate models to facilitate multiscale and multiphysics modeling. We will implement this new capability as part of the Multiphysics Object-Oriented Simulation Environment (MOOSE) so that every application based on the MOOSE framework will have access to it.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31565_TechnicalAbstract_2024CFATechnicalAbstract24-31565.pdf
24
University of Illinois at Urbana-ChampaignResearch and DevelopmentModeling and Simulation$1,098,000
We propose to develop the fundamental methods and techniques for unstructured adaptive mesh refinement with Monte Carlo tallies. This work enables a transformative leap forward in speed, accuracy, and robustness to enhance the contribution of high-fidelity radiation transport to advanced simulation. Adaptive refinement is deployed on a challenging multiphysics simulation, cascading heat pipe failure, to study acceleration and stabilization properties.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-32112_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-32112.pdf
24
Pennsylvania State UniversityResearch and DevelopmentNon-Traditional and Non-electric Applications$998,793
This project aims to design and test a micro-nuclear reactor for high-temperature portland cement clinker production, a process responsible for 6%-8% of global CO2 emissions. Leveraging advanced reactors' heat output, the project explores TRISO-based nuclear microreactor core modifications and new working fluids for heat pipes. The research addresses uncertainties in micro-nuclear reactor deployment for clinker production and investigates high-efficiency heat exchanger designs.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31754_TechnicalAbstract_2024CFATechnicalAbstract24-31754.pdf
24
Massachusetts Institute of TechnologyResearch and DevelopmentNuclear Fuel Recycle Technologies$999,999
Establishing an efficient, safe, secure, and economical Molten-Salt Reactor (MSR) fuel cycle is imperative for MSR implementation. Molten salt fuel recycling technology requires predictive knowledge of the chemical and physical behavior of lanthanide and actinide ions with different oxidation states dissolved in solvent salts. A combination of off-gas and X-ray measurements with machine-learning simulations will be used to produce predictive modeling of separation and recovery conditions.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31643_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31643.pdf
24
Pennsylvania State UniversityResearch and DevelopmentNuclear Fuel Recycle Technologies$1,000,000
To use carbonate-peroxide chemistries to develop a pre-processing method for used uranium-based fuels that enables the subsequent use and optimization of current solvent extraction reprocessing schemes. Using simple precipitation, this innovative method provides an initial, bulk separation of uranium from fission products and actinides.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31413_TechnicalAbstract_2024CFATechnicalAbstract24-31413.pdf
24
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Development and Plant Optimization$1,100,000
Flexible operation of the energy grid of the future introduces uncertainty in determining the optimal operating conditions of Pebble Bed Reactors. The proposed work will help to address these challenges and enable more economical operation by providing the tools to determine of optimal fuel reloading strategy through pebble identification and tracking.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31778_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31778.pdf
24
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Development and Plant Optimization$1,000,000
MSRs, FHRs, and HTGRs have tritium production rates 10 to 10,000 times larger than LWRs. Objective of this project is to: • Quantify the concentration of tritium in graphite in new generation FHRs and HTGRs as a function of time and operational conditions • Assess the impact of the tritium content in graphite on reactor physics during normal operations and safety transients • Quantify tritium release rates and release kinetics during reactor transients inducing temperature increases
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31644_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31644.pdf
24
University of MichiganResearch and DevelopmentReactor Development and Plant Optimization$1,100,000
The primary objectives of this proposed research are to better understand NC flow phenomena and heat transfer under both D-LOFC and P-LOFC accidents in the FMR, produce experimental data in a well-scaled integral-effects test facility for the two accidents, and develop and validate predictive CFD models for NC flow phenomena in both accidents.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31551_TechnicalAbstract_2024CFATechnicalAbstract24-31551.pdf
24
University of Wisconsin-MadisonResearch and DevelopmentReactor Development and Plant Optimization$1,000,000
The present proposal aims to experimentally investigate the thermal-hydraulics performance of liquid sodium heat pipes applied to microreactors, with a focus on exploring different design parameters, effects of different parameters on operating performance and understanding the evolution and impact of different failure modes.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31995_TechnicalAbstract_2024CFATechnicalAbstract24-31995.pdf
24
Virginia Polytechnic Institute and State UniversityResearch and DevelopmentReactor Development and Plant Optimization$1,000,000
NaF-KF-UF4 fuel salt will be selected to study graphite-salt interactions and impact of the existence of fission products (FPs) and corrosion products on the interactions at different temperatures and pressures. Fundamental mechanisms of graphite-salt interaction and degradation will be understood.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31998_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31998.pdf
24
Massachusetts Institute of TechnologyResearch and DevelopmentSpent Fuel, Waste Science & Technology and Integrated Waste Management System$800,000
The objective of this project is to develop machine learning (ML) and AI toolsets to effectively expand the global sorption database – the datasets collected by multiple institutions around the world – and to assimilate these datasets into the uncertainty quantification (UQ) in the performance assessment (PA) of nuclear waste repositories.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31545_TechnicalAbstract_2024CFATechnicalAbstract24-31545.pdf
24
Texas A & M University-College StationResearch and DevelopmentSpent Fuel, Waste Science & Technology and Integrated Waste Management System$1,000,000
Fundamental, experimental, and numerical investigations will be conducted to advance the current understanding of the impact of high temperature (i.e., up to ~200 °C) on the inhomogeneity of clay buffers and creep behavior of compacted bentonites intended for the isolation of high-level nuclear waste (HLW) and spent nuclear fuel (SNF). We will advance the current understanding of THMC processes related to HLW/SNF disposal in a generic mined geologic repository.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31671_TechnicalAbstract_2024CFATechnicalAbstract24-31671.pdf
24
University of Illinois at Urbana-ChampaignResearch and DevelopmentSpent Fuel, Waste Science & Technology and Integrated Waste Management System$1,000,000
The proposed work plan will develop nondestructive examination (NDE) methods that develop and evaluate linear and nonlinear resonant ultrasound spectroscopy methods (such as NRUS, NIRAS, etc.) to cold spray (CS) repaired dry shielded canister (DSC) wall structures. With the support of our partners from Pacific Northwest National Laboratory (PNNL) and Oak Ridge National Laboratory (ORNL), we will perform technology development and validation on plain and cold spray-repaired DSC wall specimens.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31494_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31494.pdf
24
University of Notre DameResearch and DevelopmentSpent Fuel, Waste Science & Technology and Integrated Waste Management System$1,000,000
This proposed project will quantify the solubility and speciation of Np and Pu under temperatures, ionic strengths, and pH values that are relevant to the generic repository concept. The major deliverable will be full thermodynamic descriptions of the studied systems, which will lead to improved radionuclide transport models and support the development of a sound technical basis for the geologic disposal of spent nuclear fuel and other actinide-bearing wastes.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31738_TechnicalAbstract_2024CFATechnicalAbstract24-31738.pdf
24
North Carolina State UniversityResearch and DevelopmentStrategic Needs Blue Sky$600,000
The overarching goal of the proposed research is to advance our fundamental understanding of molten salts by combining ultrafast spectroscopic experiments with high fidelity atomistic simulations. The proposed research will introduce a new experimental technique to the study of molten salts that will directly measure ion kinetics, specifically, terahertz time-domain spectroscopy (THz-TDS), which will further validate AIMD as a predictive modeling tool.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31587_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31587.pdf
24
Purdue UniversityResearch and DevelopmentStrategic Needs Blue Sky$600,000
Most two-phase flow analyses have been performed in straight vertical-upward pipes. However, nuclear reactor systems include piping with different geometric components, such as elbows or U-bends, as well as changes in flow orientations. The proposed work performs experiments in a scaled test facility existing at the institution's lab to investigate the effects of flow orientations and geometries relevant to nuclear reactor systems on the hydrodynamics of two-phase flow.
  
https://neup.inl.gov/FY24%20CINR%20RD%20Abstracts/CFA-24-31525_TechnicalAbstract_2024CFATechnicalAbstractCFA-24-31525.pdf
24
Virginia Polytechnic Institute and State UniversityResearch and DevelopmentStrategic Needs Blue Sky$500,000
The project aims at advancing the interface-resolved simulation capabilities for the two-phase flows found in various nuclear engineering applications. We will develop a comprehensive, high-resolution, interface-resolved database emphasizing bubble dynamics and bubble interaction mechanisms. The data will be used to validate the sub-grid models implemented in an interface-resolved simulation tool to improve simulation accuracy by developing physics-based coalescence models.

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