Skip Navigation LinksFY19_RandD_Awards

​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​​FY 2019 Research and Development Awards

DOE is awarding more than $28.5 million through its Nuclear Energy University Program (NEUP) to support 40 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 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.      
 

NEUP 2019 R&D Award Abstracts
  
  
  
  
  
  
  
Description
  
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17150_TechnicalAbstract_2019CFATechnicalAbstractCFA19-17150.pdf
19
Oregon State UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000.00

This project will further develop the understanding of nuclear fuel reprocessing using Co-Decontamination (CoDCon). Radiolytic degradation products of tributylphosphate, nitric acid, redox buffer, masking agent, and water greatly affect the redox speciation, complexation and partitioning of the recycled metals. Fundamental understanding of chemical speciation and partitioning of Neptunium and Zerconium under such conditions is required.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16848_TechnicalAbstract_2019CFATechnicalAbstract19-16848.pdf
19
University of UtahResearch and DevelopmentFuel Cycle Research and Development$799,031.00

This proposed research will investigate high-surface area (>300 m2/g) metal-functionalized membranes. These novel chemically durable and mechanically robust membranes are formed using an aqueous fabrication process, which results in an interconnected porosity that is highly controllable, providing hierarchical structures ranging from the nano- to micrometer-scales.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17002_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17002.pdf
19
University of South CarolinaResearch and DevelopmentFuel Cycle Research and Development$800,000.00

To enable advanced nondestructive characterization techniques for light water reactor fuels that can be applied to the cladding coating, a remote nondestructive evaluation post irradiation inspection approach will be developed. This technique will measure the cladding coating layer thickness and detect defects within the cladding such as corrosion, micro-cracking and delamination.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17276_TechnicalAbstract_2019CFATechnicalAbstract19-17276.pdf
19
University of Tennessee at KnoxvilleResearch and DevelopmentFuel Cycle Research and Development$799,989.00

The microstructural evolution of advanced fuel (uranium carbide and uranium nitride) under fission-fragment type radiation has not been studied and remains unclear. This project will utilize advanced synchrotron X-ray characterization using microgram samples to obtain detailed nanoscale information on radiation-induced volumetric swelling and microstrain.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17381_TechnicalAbstract_2019CFATechnicalAbstractRPA-19-17381.pdf
19
University of Minnesota, Twin CitiesResearch and DevelopmentFuel Cycle Research and Development$800,000.00

This project will develop a high throughput assessment of creep behavior of advanced nuclear reactor structural alloys by nano/microindentation. Experimental datasets will inform polycrystalline deformation models to predict material response over a variety of creep conditions.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16987_TechnicalAbstract_2019TechnicalAbstract19-16987.pdf
19
North Carolina State UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000.00

This project will develop a miniature creep machine to collect rapid thermal creep and load relaxation data for two selected ferritic alloys under "as-received" and irradiated conditions. Fast and accurate measurements of creep deformation are essential for qualifying new alloys for long term use in current and next generation reactors.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16549_TechnicalAbstract_2019CFATechnicalAbstract16549.pdf
19
University of PittsburghResearch and DevelopmentFuel Cycle Research and Development$500,000.00

This project intends to provide accurate thermal conductivity and thermal diffusivity data with microstructure characterization of metallic (U-Pu-Zr) fuel as a function of burnup and attain fundamental understanding of the thermal conductivity of the irradiated fuel to inform and validate computational models. This will be accomplished using an innovative thermal wave technique in the Transient Reactor Test Facility at the Idaho National Laboratory, with the Minimal Activation Reusable Capsule Holder.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16583_TechnicalAbstract_2019CFATechnicalAbstract19-16583.pdf
19
The Ohio State UniversityResearch and DevelopmentFuel Cycle Research and Development$499,997.00

This project will perform systematic diffusion studies on both neutron-irradiated and unirradiated accident tolerant fuel samples to obtain precis
e diffusion coefficients. This will result in a precise evaluation of the pure neutron irradiation effect on diffusion in these systems and enable accurate life prediction of the accident tolerant fuels.
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17395_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17395.pdf
19
Pennsylvania State UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000.00

This project will model and analyze the limits of detection for the diversion of nuclear materials from a molten salt reactor (MSR) fuel cycle. MSR depletion under a range of uranium and/or plutonium diversion to quantify the resulting differences in salt composition will be evaluated. Sensors will also be investigated to quantify fuel salt contents and correlate the outputs with the reactor models to predict diversion detection. Results will be coupled with robust uncertainty analysis to determine limits of detection.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17350_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17350.pdf
19
University of VirginiaResearch and DevelopmentFuel Cycle Research and Development$799,027.00

The specific goals of this project are to: (a) validate the maximum pit size model for dry storage canister relevant corrosion conditions as well as quantifying the effects of limited cathodic current on stress corrosion cracking (SCC) kinetics, (b) demonstrate a means to quantitatively rank the risk of SCC based on measurable parameters, (c) perform probabilistic predictions of SCC growth, and (d) validate the model predictions.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17461_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17461.pdf
19
North Carolina State UniversityResearch and DevelopmentNuclear Energy Research and Development$400,000.00

This project will develop integral benchmarks that aim to examine thermal neutron scattering data for graphite (ideal and nuclear), light water, and molten salt. The benchmark evaluations will be contributed to the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP) database.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16739_TechnicalAbstract_2019CFATechnicalAbstract19-16739.pdf
19
Rensselaer Polytechnic InstituteResearch and DevelopmentNuclear Energy Research and Development$400,000.00

The objective of this project is to improve the accuracy of neutronics simulation of lead-based systems by improving the nuclear data of lead isotopes. The nuclear data for lead will be reevaluated with emphasis of the intermediate and fast energy regions that are
required by reactor applications currently sought by several industrial entities. The deliverables of this
project are new lead isotopes evaluations that will be candidates for inclusion in a future Evaluated Nuclear Data Library (ENDF) release.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16743_TechnicalAbstract_2019CFATechnicalAbstract19-16743.pdf
19
University of OklahomaResearch and DevelopmentNuclear Energy Research and Development$390,393.00

This project will enable deployment of advanced nuclear technologies by developing a model, and an accompanying web-based tool that can be utilized by technology entrepreneurs, that identifies public support for siting new nuclear technologies at very local spatial scales across the US. The model will employ hierarchically structured, post stratified analysis of the largest US pooled-time series dataset on geocoded public support for nuclear technologies.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16995_TechnicalAbstract_2019CFATechnicalAbstract19-16995.pdf
19
University of Tennessee at KnoxvilleResearch and DevelopmentNuclear Energy Research and Development$799,995.00

The proposed research will develop a robust cyber-attack detection system (CADS) for monitoring digital instrumentation and control (I&C) systems. The project will develop a robust research tool for evaluating cyber defense of digital I&C systems and provide a framework for a cyber-attack detection system that provides continuous assurance of the security of digital I&C systems in nuclear power plants (NPPs).


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16879_TechnicalAbstract_2019CFATechnicalAbstract19-16879.pdf
19
Brigham Young UniversityResearch and DevelopmentNuclear Energy Research and Development$799,933.00

This project develops new capabilities of design and dispatch optimization of nuclear hybrid energy systems (NHES) in the "Risk Analysis Virtual Environment (RAVEN)" modelling software. Blended (physics-based and data-driven) machine learning will be applied to forecast demand and production of thermal and electrical loads. Two experimental case studies are proposed to test the software developments with a lab-scale thermal energy storage and with a large district energy system. As a final step, the software developments will be generalized to other NHES.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17327_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17327.pdf
19
University of Texas at DallasResearch and DevelopmentNuclear Energy Research and Development$800,000.00

The overarching objective of this project is to develop a multi-timescale nuclear-renewable hybrid energy systems (N-R HESs) operations framework to provide different types of grid products. The project will model and analyze the capabilities of N-R HESs to provide power grid services at different timescales ranging from seconds to days, such as day-ahead unit commitment, flexible ramping (5-45 minutes), regulation reserves (1-5 minutes), and frequency response (less than seconds).


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17219_TechnicalAbstract_2019CFATechnicalAbstract19-17219.pdf
19
University of New MexicoResearch and DevelopmentNuclear Energy Research and Development$400,000.00

This project will use the results of integral benchmark experiment to inform differential nuclear data evaluations and improve the predictive capability of modeling and simulation (M&S) tools. This goal will be accomplished by developing capabilities to assess the sensitivity of integral benchmark results to evaluated nuclear data parameters, and by using data assimilation tools to directly adjust the evaluated data parameters and improve the accuracy of M&S tools.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17173_TechnicalAbstract_2019CFATechnicalAbstract19-17173.pdf
19
North Carolina State UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

The objective of this work is to (i) propose and develop a new Nickel (Ni) based Oxide Dispersion-Strengthened (ODS) alloy that can be used for structural applications in Molten Salt Reactor (MSR) and other nuclear reactor harsh environments, (ii) to demonstrate that its high temperature mechanical properties are adequate for MSR operating temperatures, (iii) to demonstrate its radiation damage resistance through ion irradiation testing and (iv) to demonstrate its improved corrosion resistance in MSR environment.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17247_TechnicalAbstract_2019CFATechnicalAbstract17247.pdf
19
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

This project will improve the accuracy, information density, and resolution of the mineralogical spatial maps currently used as inputs to the concrete modeling code MOSAIC by exploiting new characterization methods. This will build fundamental knowledge about amorphization and hydrolysis of minerals caused by radiation and provide information on softening and porosity. This work is important to the Light Water Reactor Sustainability (LWRS) program because it will result in a highly informed approach to assess concrete’s tolerance to radiation.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17093_TechnicalAbstract_2019CFATechnicalAbstract17093.pdf
19
University of California, Los AngelesResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will develop unprecedented multi-modal imaging methodologies that integrate multiple microscopy techniques. The team will develop a generalizable protocol for quantifying the changes in physical properties and chemical durability of concrete and concrete constituents (minerals and aggregates) following radiation exposure. The imaging analyses will be input into the MOSAIC framework to reveal the nature and extent of degradation that is expected to result. The outcomes offer insights that are needed to enable and inform second license renewals.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17167_TechnicalAbstract_2019CFATechnicalAbstract19-17167.pdf
19
University of FloridaResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$797,861.00

Researchers will construct a validated computational model for He bubble growth on grain boundaries in irradiated Fe-Ni-Cr microstructures, including intergranular fracture, as a function of material conditions and welding heat input. This model will be based on the phase-field methodology, leveraging numerical solvers in the MOOSE simulation platform, with critical inputs and validation provided by both atomic-level simulations and experiments.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16802_TechnicalAbstract_2019CFATechnicalAbstract16802.pdf
19
University of MichiganResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$400,000.00

Researchers will investigate the use of variable flow controllers and a variable reflector as passive or semi-autonomous reactivity control mechanisms for multi-module HTGR type special purpose reactors. This applies to the commercially developed special purpose reactor concepts from HolosGen. The incorporation of these systems will reduce the movable parts count and enable more robust load follow capabilities over broader power ranges and local and global reactivity control.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17185_TechnicalAbstract_2019CFATechnicalAbstractRPA-19-17185.pdf
19
Massachusetts Institute of TechnologyResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$400,000.00

Researchers will demonstrate a detection-prediction-feedback framework for nuclear system autonomous control. It will adopt multiple detector channels to enable control feedback to spatially dependent perturbations. It will also utilize high-fidelity solutions trained surrogate models for real-time prediction and decision-making. In addition to the method development, the proposal will entail a first-of-a-kind engineering demonstration using the MIT Graphite Exponential Pile (MGEP).


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16980_TechnicalAbstract_2019CFATechnicalAbstract19-16980.pdf
19
Auburn UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$400,000.00

Researchers will determine how to best use laser-powder bed fusion additive manufacturing methods for generating radiation-resistant channel/pore-embedded structures from Inconel (alloy 625 or 718) nickel-based superalloys for special purpose reactor (i.e. very small modular reactor) heat exchangers.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16909_TechnicalAbstract_2019CFATechnicalAbstract16909.pdf
19
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will obtain the thermophysical, thermochemical, and transport properties, construct the phase diagrams, and build empirical physical models of molten salts that are relevant to Molten Salt Reactors (MSRs) with first-principles accuracy using molecular dynamics simulations driven by machine-learned high-dimensional neural network potentials combined with neutron/X-ray scattering and thermodynamic experimental validations.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17467_TechnicalAbstract_2019CFATechnicalAbstract19-17467.pdf
19
University of Nevada, RenoResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will develop a methodology to accurately determine the structure and speciation of the molten salt electrolyte using laboratory-based spectroscopic techniques (Raman and UV-Vis-NIR) and synchrotron-based (scattering and absorption) techniques, in combination with computational modeling.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16811_TechnicalAbstract_2019CFATechnicalAbstract19-16811.pdf
19
University of Wisconsin-MadisonResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will explore three different areas that will help to improve commercialization of SFRs and to aid in testing for the VTR. These include: 1. Advancement in understanding of low prandtl number heat transfer 2. Testing of compact heat exchangers for use with sodium 3. Development of in pool submersible flow meters.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16754_TechnicalAbstract_2019CFATechnicalAbstract19-16754.pdf
19
Massachusetts Institute of TechnologyResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$762,823.00

Researchers will test candidate FeCrSi and F/M alloys in a new, simultaneous corrosion/radiation facility to try to identify an alloy that will satisfy all requirements for Lead Fast Reactor structural materials. Microstructural characterization, mechanical property testing, and corrosion tests, both during irradiation and following ion/He pre-conditioning, will assess how irradiation affects corrosion, potentially slowing it.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17037_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17037.pdf
19
Purdue UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$799,832.00

Researchers will perform a series of experiments to simulate HTGR reactor building response due to a break in the primary coolant boundary in a well-scaled test facility to obtain spatial distribution of oxygen concentration, perform analysis of the whole system response with 1-D thermal hydraulics codes and use CFD to make detailed localized predictions. The tests will be carried out with different locations and sizes of the breaks to create various vent and flow paths in the reactor cavity.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17168_TechnicalAbstract_2019CFATechnicalAbstract17168.pdf
19
Vanderbilt UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$799,989.00

Researchers will combine insights from the Molten Salt Reactor Experiment with decades of advancements in applicable technologies into an enhanced Sampler Enricher (SE) concept to develop and test a flexible, reliable, and workable design. The prototype will then be tested in an existing salt loop.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16954_TechnicalAbstract_2019CFATechnicalAbstract19-16954.pdf
19
University of Wisconsin-MadisonResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will use a thin-layer activation technique for the first time in molten salts, on 316H samples placed in natural convection and forced flow loops. The individual and synergistic effects of corrosion, irradiation and thermo-mechanical treatments will be evaluated in-situ to predict component service lifetimes and design limits. The effects of molten chloride flow velocity will also be assessed.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17192_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17192.pdf
19
Abilene Christian UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$762,246.00

Researchers will develop a novel mechanical filtration system. The project will include the collection of filter media performance data and filter regeneration performance data for a novel sintered nickel-based filter prototype. The project will also provide a filter design that facilitates remote filter removal, cooling, replacement, and assay of fissile material hold-up in the filter media.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17231_TechnicalAbstract_2019CFATechnicalAbstract19-17231.pdf
19
University of Tennessee at KnoxvilleResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will provide an effective design evaluation approach based on prevention of concurrent triggering conditions to eliminate common-cause failures (CCF) and enable qualification of digital I&C technology for application in nuclear plant modernization. The research involves classifying commonality among digital devices, categorizing faults and triggering conditions, determining fault-trigger relationships, and defining preventive design measures to resolve the potential for CCF.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16391_TechnicalAbstract_2019CFATechnicalAbstract19-16391.pdf
19
Duke UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00

Researchers will develop a dependable, autonomous or semi-autonomous (i.e. low human involvement), and minimally disruptive framework for monitoring equipment and components in nuclear reactors. The project will develop GUARDIAN; a robust active sensing framework through the integration of model-based inference and mobile actuating/sensing robots.


  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16298_TechnicalAbstract_2019CFATechnicalAbstract16298.pdf
19
University of Illinois at Urbana-ChampaignResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00
Researchers will develop an integrated probabilistic risk assessment decision-making algorithm to support risk-and-cost-informed decision-making related to the deployment of new technologies. The project will enhance the financial analysis module and the challenging interface of social and technical systems to advance the algorithm. The project will conduct a case study for evaluating the safety impact and cost-effectiveness of FLEX strategies to support operational flexibility.
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17087_TechnicalAbstract_2019CFATechnicalAbstract19-17087.pdf
19
University of Tennessee at KnoxvilleResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00
Researchers will provide a holistic framework for cost-minimizing risk-informed maintenance planning, including inspection. They will develop a two-tier framework that coarsely minimizes the total maintenance cost during the remaining normal operating cycle and uses the outputs of the first model to maximize the financial impact of these activities in the short term.
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17355_TechnicalAbstract_2019CFATechnicalAbstract19-17355.pdf
19
University of PittsburghResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00
Researchers will develop a versatile liquid lead testing facility and test material corrosion behavior and ultrasound imaging technology in liquid lead. This will support deployment of a lead cooled-fast reactor which has several advantages in safety, performance and economic viability over other Generation IV reactor concepts. Outcomes of the project will directly support the DOE-NE’s mission of developing an advanced reactor pipeline.
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17251_TechnicalAbstract_2019CFATechnicalAbstract19-17251.pdf
19
Idaho State UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$799,815.00
Researchers will characterize the strength of TRISO-coated particle layers and interfaces using FIB micro-machining and in-TEM tensile testing. Tensile test samples from coating layers of (1) unirradiated surrogate (fuel) TRISO particles, (2) unirradiated fueled TRISO particles and (3) irradiated fueled TRISO particles will be studied. Results of this project will both benefit and leverage the AGR Program.
  
https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17183_TechnicalAbstract_2019CFATechnicalAbstract19-17183.pdf
19
City College of New YorkResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$800,000.00
Researchers will conduct separate effects tests to obtain experimental validation data on mixing of helium and air in reactor building cavities during and after blowdown in HTGRs. Air and helium concentrations, and gas mixture velocity and temperature fields will be measured in simulated reactor cavities. An existing helium flow loop will be used as the source of high pressure/high temperature helium for injection into the cavities and different break configurations will be experimentally investigated.
  
https://neup.inl.gov/FY%202019%20Abstracts1/2019%20CFA%20Technical%20Abstract%2017416.pdf
19
University of MichiganResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$400,000

Researchers will design an experimental facility and execute experiments on heat pipes for micro-reactors. The advantage of liquid metal heat pipes is that they can operate at very high temperatures (around the boiling point of the working fluid) and are fully passive heat removal devices. Experimental results will be used produce recommendations to resolve thermo-mechanical stresses on micro-reactors cores following failure of multiple heat pipes.

  
https://neup.inl.gov/FY%202019%20Abstracts1/2019%20CFA%20Technical%20Abstract%20%2019-17109.pdf
19
Brigham Young UniversityResearch and DevelopmentReactor Concepts Research and Development and Demonstration (RCRD&D)$798,291

Researchers will use first principles molecular dynamics (FPMD) simulations on molten salts containing impurities including fuel, fission products, and corrosion products. These will be used to develop a classical molecular dynamics (CMD) potential. CMD will then be used to predict properties for a wide variety of salt compositions and temperatures, and physical property measurements will be performed to validate those predictions. Property correlations will be developed from this data.

 

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