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​​​​​​​​​FY 2015 Research and Development Awards

The Energy Department is awarding over $30 million through its Nuclear Energy University Programs (NEUP) to support 43 university-led nuclear energy research and development projects to develop innovative technologies and solutions. These projects will be led by 31 U.S. universities in 23 states.

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

NEUP 2015 R&D Award Abstracts
  
  
  
  
  
  
  
Description
  
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8603_Filtered.pdf
15
California State University, Long BeachResearch and DevelopmentFuel Cycle Research and Development$800,000

Researchers will establish a quantitative connection between ligand structure and the reactions of the organic radicals involved in radiolytic degradation to ultimately allow for the design of “self-protecting” liquid-liquid formulations. This project will provide a predictive capability for radiolytically induced degradation in current and future solvent systems.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8603%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8514_Filtered.pdf
15
California State University, Long BeachResearch and DevelopmentFuel Cycle Research and Development$800,000

Researchers will develop a fundamental understanding of the chemical kinetics relevant to separation processes by measuring ligand complexation rate constants for both lanthanides and actinides in the aqueous and organic phases. These experiments will provide essential kinetic and mechanistic information required for developing a simplified, single-step recovery of transuranic elements.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8514%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8119_Filtered.pdf
15
Colorado School of MinesResearch and DevelopmentFuel Cycle Research and Development$375,000

Researchers will develop metal organic framework (MOF) membranes that will be capable of effectively separating Kr from Xe with high flux and selectivity. This project may result in the development of membranes that will constitute a viable energy saving approach for the effective removal of Kr during the processing of used nuclear fuel.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8119%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8347_Filtered.pdf
15
Massachusetts Institute of TechnologyResearch and Development Fuel Cycle Research and Development$800,000

Researchers will develop, manufacture, and weld a new multimetallic layered composite (MMLC) for enhanced severe accident tolerance and manufacturability in LWRs. Layers of stainless steel (facing the coolant) and Zircaloy (facing the fuel) will be separated by barrier layers of Cr and Nb. Severe accident testing in 1200C steam, LWR autoclave testing, and ion irradiation studies will demonstrate the MMLC's microstructural stability.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8347%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8112_Filtered.pdf
15
Missouri University of Science and TechnologyResearch and DevelopmentFuel Cycle Research and Development$799,806

Researchers will study the mechanisms for microstructural development and properties of multi-phase, glass-ceramic materials that form when waste-loaded borosilicate glasses are cooled from above their liquidus or consolute temperatures through the glass transition temperature. The project will apply these tools to modified compositions to maximize the formation of the desirable crystalline phases.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8112%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8265_Filtered.pdf
15
Northwestern UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000

Researchers will enhance the formability of nanostructured ferritic alloys (NFAs) such that high-strength thin-walled claddings can be manufactured successfully and economically to be used in future reactors. The project will study the effects of continuous and pulsed electric currents on the deformation behavior of Fe-14Cr based NFA steel. The findings will be used to establish innovative fabrication processes including electrically-assisted extrusion and rolling.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8265%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8126_Filtered.pdf
15
Pennsylvania State UniversityResearch and DevelopmentFuel Cycle Research and Development$800,000

Researchers will investigate the fundamental properties of novel liquid metal electrodes for separation of alkali/alkaline-earth fission products in LiCl-KCl electrolyte. The project will further the development of pyroprocessing by maximizing salt recycle and providing a method for recovery of alkali/alkaline-earth fission products as oxides (as opposed to chlorides) which will allow them to be encapsulated in a more conventional glass wasteform.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8126%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8074_Filtered.pdf
15
The Ohio State UniversityResearch and DevelopmentFuel Cycle Research and Development$799,969

Researchers will develop a novel in-salt sensor that uses electrochemistry to pre-concentrate the actinides onto the sensor to measure the actinides concentration in a high temperature and high radiation field represented by a molten salt environment. The ability to monitor actinides to prevent misuse is critical to enhancing the control of nuclear materials.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8074%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8717_Filtered.pdf
15
University of AlabamaResearch and DevelopmentFuel Cycle Research and Development$553,971

​Researchers will investigate the fundamental interactions of the amidoxime (R-C(NH2)=NOH) functional group with metal ions found in seawater using a combined approach of single crystal X-ray diffraction and spectroscopy to understand the origin of the selectivity of amidoxime resins for uranyl ([UO2]2+] ions and establish structural benchmarks for interpretation of spectroscopic studies on actual sorbents to aid in identifying specific sorbent-metal interactions.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8717%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8439_Filtered.pdf
15
University of California, BerkeleyResearch and DevelopmentFuel Cycle Research and Development$800,000

Researchers will develop a fundamental understanding of the macroscopic behavior of SiC-SiC composite structures before and after irradiation based on the microscopic property changes of each individual component (SiC matrix, fiber and interface). SiC-SiC composites will be tested in the as-fabricated condition, after being subjected to neutron and ion irradiation, micro-cracking, and oxidation.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8439%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8536_Filtered.pdf
15
University of California, RiversideResearch and DevelopmentFuel Cycle Research and Development$450,000

Researchers will quantitatively predict stability of uranium species and thermochemistry (free energy, entropy, and enthalpy) of uranium binding with amidoxime ligands in seawater conditions. To achieve the goal, advanced simulation techniques including all-atom molecular dynamics, free-energy calculations, and the hybrid quantum mechanical/molecular mechanical approach will be employed to explicitly include water molecules and common seawater ions in the simulation.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8536%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8286_Filtered.pdf
15
University of FloridaResearch and DevelopmentFuel Cycle Research and Development$799,765

Researchers will build and demonstrate a prototype detector device capable of unambiguously verifying the declared content of dry casks in a non-intrusive manner for the safeguarding and monitoring of used fuel storage installations. This will be achieved through a neutron spectroscopy and imaging system using high-efficiency Helium-4 (4He) gas scintillation fast neutron detectors.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8286%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8663_Filtered.pdf
15
University of Maryland, College ParkResearch and DevelopmentFuel Cycle Research and Development$600,000

Researchers will produce efficient adsorbents of uranium from seawater in seeking to optimize the functional ligands, the polymeric substrates, the grafting conditions and the adsorption/desorption durations based on sound chemical understanding. The result will be adsorbents that can be used through multiple cycles of uranium adsorption without significant degradation of the adsorbents capacity and selectivity for uranium.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8663%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8111_Filtered.pdf
15
University of Nevada, Las VegasResearch and DevelopmentFuel Cycle Research and Development$798,877

​Researchers will investigate the thermochemistry of used fuel Zr cladding components chlorides as well as their activation products and residual radionuclide metal chlorides to provide fundamental data that will support the development of a chlorination process for the purification of ZrCl4. Understanding the chemistry of these chloride species will provide process development guidance for the purification of Zr cladding.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8111%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8323_Filtered.pdf
15
University of Tennessee at KnoxvilleResearch and DevelopmentFuel Cycle Research and Development$793,121

​Researchers will develop and demonstrate a process to purify zirconium tetrachloride obtained from the direct chlorination of used Zircaloy cladding materials from used nuclear fuel rod assemblies. This study will increase understanding of purification protocols that will allow zirconium chloride to be recycled further. Increased recycling capability would significantly reduce the amount of high level waste associated with light water reactors.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8323%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8752_Filtered.pdf
15
University of Tennessee at KnoxvilleResearch and DevelopmentFuel Cycle Research and Development$400,000

​ Researchers will use scoping ion and neutron irradiations to explore the structural stability and thermal conductivity of model high thermal conductivity fuels consisting of CeO2 and either Al2O3 (BeO surrogate) or SiC. Issues associated with thermal conductivity degradation (including micro cracking effects) and general phase stability of fuel systems will be examined.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8752%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8243_Filtered.pdf
15
University of Wisconsin, MadisonResearch and DevelopmentFuel Cycle Research and Development$797,889

​Researchers will use state of the art experimental characterization techniques and multi-scale methodology (developed within the MOOSE-MARMOT-BISON framework) to provide scientific basis for predictions of swelling and microcracking in SiC cladding as a function of temperature and irradiation histories. Predicting swelling and microcracking will further the potential for accident tolerant SiC cladding to be used in light water reactors.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8243%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8081_Filtered.pdf
15
Washington State UniversityResearch and DevelopmentFuel Cycle Research and Development$799,911

​Researchers will develop a fundamental and transformative understanding of the crystallization mechanisms in complex glass-ceramic high level waste (HLW) wasteforms,. This understanding will underpin the maturation of glass ceramic manufacture, by linking process variables to molecular scale mechanisms, enabling reliable production of wasteforms to the desired specification.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8081%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8743_Filtered.pdf
15
North Carolina State UniversityResearch and DevelopmentMission Supporting Transformative Research: Integral Benchmark Evaluations$400,000

​Researchers will conduct a benchmark evaluation using data generated during the “IFR Safety Tests M2 and M3” that were conducted in the TREAT reactor. The evaluations will be conducted using the NEAMS MAMMOTH tool, which couples the neutron transport application RATTLESNAKE to the fuels performance application BISON within the MOOSE framework. Both the steady and transient conditions of the M2 and M3 tests will be evaluated.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8743%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8210_Filtered.pdf
15
Kansas State UniversityResearch and Development Nuclear Energy Advanced Modeling and Simulation (NEAMS)$799,198

​Researchers will instrument the University of Wisconsin Nuclear Reactor with micro-pocket fission detectors (MPFDs) to measure 3-D flux distributions. The measurements will be compared to simulation using PROTEUS from the NEAMS toolkit. MPFDs are small, which leads to low gamma-ray sensitivity and small flux perturbations. A 3-D array of MPFDs and standard reactor instrumentation will be used to capture highly-resolved flux and temperature distributions for several steady-state and transient conditions.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8210%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/2015%20CFA%20Technical%20Abstract%20CFA-15-8576.pdf
15
North Carolina State UniversityResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$800,000

​Researchers will perform experimental investigation of the fission gas (xenon and krypton) release phenomenon in nuclear fuel. The experimental findings will be utilized to investigate and validate the FGR models that are currently implemented in the BISON fuel performance code. Consequently, modifications to BISON’s FGR models may be introduced and simulations of fuel performance behavior conducted.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8576%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8101_Filtered.pdf
15
Rensselaer Polytechnic InstituteResearch and Development Nuclear Energy Advanced Modeling and Simulation (NEAMS)$799,993

Researchers will develop a set of benchmark validation experiments for multiphysics coupling by exploiting the inherent flexibility of the Rensselaer Polytechnic Institute Reactor Critical Facility (RCF). This project will use targeted experiments to validate the coupling between neutronics, thermal hydraulics, and structural mechanics routines present in the NEAMS Reactor Product Line toolkit.​

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8101%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8229_Filtered.pdf
15
Rensselaer Polytechnic InstituteResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$800,000

​Researchers will perform experimental validation of the NEAMS tool MARMOT for predicting thermal transport and fuel fracture. By performing extensive thermal transport and fracture experiments on well-controlled microstructures of sintered UO2, the impact of microstructure on thermo-mechanical properties of sintered UO2 and mechanistic understanding will be achieved. The high quality experimental data will directly benchmark the MARMOT code by evaluating the thermal transport and fracture models.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8229%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/2015%20CFA%20Technical%20Abstract%208208.pdf
15
University of Massachusetts, LowellResearch and DevelopmentNuclear Energy Advanced Modeling and Simulation (NEAMS)$626,176

​Researchers will develop a novel accelerator for neutron transport calculations based on the spectral element methods, continuous Galerkin (CG) and discontinuous Galerkin (DG) approximations. The CG and DG methods will be used to solve the multi-group neutron diffusion equation on the coarse-mesh structure (e.g., pin-size up to assembly-size), which is then coupled with the high-order neutron transport solution to speed up the neutron transport computation.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8208%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/2015%20CFA%20Technical%20Abstract%20CFA-15-8338.pdf
15
North Carolina State UniversityResearch and DevelopmentNuclear Energy: Cyber Security R&D$800,000

​Researchers will develop a methodology for assessing the cybersecurity robustness and vulnerability of university research reactors using an actual university reactor as a test case. While the developed methodology will be specifically tested and applied using this reactor, it will be formulated as a general blueprint and used as the starting point for the assessment of university research reactors.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8338%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/2015%20CFA%20Technical%20Abstract%20CFA-15-8228.pdf
15
University of TulsaResearch and DevelopmentNuclear Energy: Cyber Security R&D$800,000

​Researchers will model the I&C system of a research nuclear reactor using the hybrid attack graph formalism and a “Honeynet” to identify cyber-security vulnerabilities present in the system and evaluate potential remediation options to defend against those vulnerabilities. This technology will be used to create specific tools to enhance university research reactors digital control, monitoring and communication systems subject to cybersecurity challenges.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8228%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8121_Filtered.pdf
15
Arizona State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,738

​Researchers will test the hypothesis that real-time imagery-based object tracking and spatial analysis, as well as human behavior modeling will significantly improve efficiency of outage control while lowering the rates of accidents and incidents. The project will examine computer vision methods and human behavior models for developing a proactive workflow management tool and integrate it into Computer-Based Procedures for supporting an Advanced Outage Control Center.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8121%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8548_Filtered.pdf
15
Colorado School of MinesResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$746,076

​Researchers will develop understanding of the mechanisms responsible for behavior of Alloy 709 under accelerated testing conditions to confidently predict long term creep and creep-fatigue behavior at the times (500,000 hours) and temperatures (550°C) of interest for fast reactor structural applications. The accelerated tests can be used to qualify the alloy for use in advanced nuclear reactor applications.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8548%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/CFA_2015_15-8205_Technical_Abstract.pdf
15
CUNY, City College of New YorkResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,993

​Researchers will study coolant flow and heat transfer in a prismatic core of a very high temperature reactor (VHTR). Natural circulation flow and heat transfer will be investigated experimentally using a helium-nitrogen mixture at temperatures up to 1,100° F and low and high pressures up to 1,000 psi. In addition, forced convection and bypass-coolant flow of helium at high graphite temperatures and the effect of air and steam ingress on radiative heat transfer will be studied experimentally.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8205%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8308_Filtered.pdf
15
North Carolina State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​A joint US/UK team will study the crack growth mechanism and failure analysis of alloy 709 under creep and creep-fatigue conditions. The study will be done through in situ heating and loading during SEM observation to evaluate the crack growth under plane stress condition and traditional methods to study the crack growth under plane strain condition.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8308%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8582_Filtered.pdf
15
North Carolina State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​Researchers will use mechanistic methods for predicting creep and creep-fatigue deformation rates/strains based on accelerated in-situ and ex-situ tests, and mesoscale dislocation dynamics simulations for Alloy 709. This research will support its qualification in the ASME code for use in advanced nuclear reactor applications.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8582%20NEUP%20Final%20Project.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8495_Filtered.pdf
15
Oregon State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​Researchers will conduct a round robin test plan for S-CO2 corrosion testing across multiple institutions and the organization of a S-CO2 Materials Group to guide future materials testing directions. Furthermore, this proposal outlines identical tests in supercritical water, testing model alloys with various composition and environmental conditions, accompanied by modeling efforts to study rate controlling mechanisms of corrosion.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8495%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8489_Filtered.pdf
15
Oregon State UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​A joint US/UK team will study thermal and irradiation-induced transformations mechanisms of Alloys 690 and 625 in order to extend Grizzly to include capabilities for modeling Ni-based alloys. The project will develop modeling tools for materials degradation in light water reactors, allowing for component replacement data and continued safe operation.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8489%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-7983_Filtered.pdf
15
Purdue UniversityResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​Researchers will develop steady-state thermal-hydraulic analysis and assembly bowing reactivity evaluation methods based on the latest transport calculation capabilities in order to overcome the limitations and improve the accuracy of current design analysis methods. The outcome of the effort will be computer programs to calculate the steady-state heat source distributions in fuel pins and assembly duct walls and to calculate the reactivity worth of assembly displacements.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-7983%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8627_Filtered.pdf
15
Texas A&M UniversityResearch and Development Reactor Concepts Research Development and Demonstration (RCRD&D)$799,613

​Researchers will establish reliable models of the thermal-hydraulics in Gas-Cooled Reactors with experimental and computational efforts. Specifically, this work will focus on providing the relationship between fluctuating velocities and temperatures in the lower plenum and their dependency on the turbulent upstream mixing in the core and collection chambers leading up to the lower plenum.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8627%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8251_Filtered.pdf
15
University of California, BerkeleyResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$400,000

​Researchers will study the feasibility of improving the passive safety and economics of sodium cooled fast reactors (SFR) by incorporating within their fuel assemblies a novel Autonomous Reactivity Control (ARC) system. It is expected that the ARC systems will enable to design even low leakage SFR cores, such as breed-and-burn cores, to be passively safe and to improve the neutron economy and economic viability of more conventional SFR.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8251%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8258_Filtered.pdf
15
University of California, Los AngelesResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$798,846

​Researchers will develop and experimentally validate a probabilistic physics-based degradation models for polymeric insulators of electric cables to be used in integrated performance and safety codes, which will help reduce the uncertainty associated with the long-term aging of cable insulation. The project will deliver a C++ based simulation code that will be readily compatible with the MOOSE/Grizzly framework developed at the Idaho National Laboratory.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8258%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8000_Filtered.pdf
15
University of California, Los AngelesResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​Researchers will quantify the impacts of irradiation on concrete degradation. The research will develop new understanding of the evolutions and manifestations of irradiation assisted aggregate concrete degradation caused by neutron exposure. This assessment will help to mitigate the risk of such degradation within the Grizzly framework, by careful integrations of nanoscale analytics and simulation.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8000%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8458_Filtered.pdf
15
University of HoustonResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000
Researchers will develop a multi-physics framework to characterize the deterioration development in concrete due to environmental and mechanical loading, and the coupling effect among transport processes and the damage of concrete. This project will develop new computational tools that will be implemented in Grizzly, an application built on the MOOSE platform, to address a variety of aging mechanisms in nuclear power plants.
https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8458%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8623_Filtered.pdf
15
University of IdahoResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,927

​Researchers will study creep-fatigue crack growth behavior in steel Alloy 709 in accelerated test conditions to predict extended service life of structural components. Extensive testing of Alloy 709 creep-fatigue specimens will be performed at elevated temperatures and applied stresses. Microstructure analysis will be performed to describe the crack propagation mechanisms. Computational models will be used to predict service of steel components.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8623%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8432_Filtered.pdf
15
University of Illinois, Urbana ChampaignResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,00

​Researchers will conduct a detailed experimental investigation of creep-fatigue crack initiation in a 709 alloy, and will also obtain a predictive failure initiation model that includes both thermo-mechanical and aging effects. The experiments will use ultra-high resolution digital image correlation to measure accumulation of plastic with cycling. The model will extend existing slip band-based energy minimization criterion to include thermal effects applicable to 709.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8432%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8599_Filtered.pdf
15
University of MissouriResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$399,187

​Researchers will investigate the release and transport mechanisms of Am-241 to understand the interactions it may have with the environment. The project will examine Am-241 through a series of accident scenarios using Am-241 aerosols that will allow researchers to understand the pathways for dose assessment. Methodologies and approaches for nuclear risk assessment for new space radioisotope power system applications will be developed.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8599%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8667_Filtered.pdf
15
University of New MexicoResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$800,000

​Researchers will investigate a novel compact double-walled twisted-tube heat exchanger (DT-HXR) design that utilizes an outer twisted tube configuration in order to enhance shell-side heat transfer and make the overall bundle more compact. Utilizing outer twisted tube geometry improves heat transfer and allows for a tube bundle that does not require support plates or anti-vibration bars.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8667%20NEUP%20Final%20Report.pdf
  
https://neup.inl.gov/SiteAssets/FY%202015%20Abstracts/R_D/NEUP_Attachments_Proposal_CFA-15-8352_Filtered.pdf
15
University of Wisconsin, MadisonResearch and DevelopmentReactor Concepts Research Development and Demonstration (RCRD&D)$799,988

​Researchers will use a graphite moderator to capture and remove tritium from the primary coolant systems of salt- and gas-cooled reactors. The team will develop electrochemical techniques to characterize tritium transport in graphite and liquid fluoride salts (including flibe), demonstrate the in-situ effectiveness of tritium absorption by the fuel elements, and develop a design for a graphite bed tritium filter that can integrate with salt-to-air heat exchangers.

https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202015/15-8352%20NEUP%20Final%20Report.pdf

FCR&D – Fuel Cycle Research and Development
NEAMS – Nuclear Energy Advanced Modeling and Simulation
​RCRD&D – Reactor Concepts Research, Development and Demonstration


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

Research & Development (R&D)

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