Projects
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NEUP CINR-18-15263: X-ray Studies of Interfacial Molecular Complexes in ALSEP Back-Extraction
The proposed project will use synchrotron X-rays to characterize the...
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NEUP CINR-18-15270: Innovative Use of Accident Tolerant Fuels (ATF) with the RCIC System to Enhance Passive Safety of Commercial LWRs
The overarching objectives of this proposal are to demonstrate new...
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NEUP CINR-18-15276: Coping Time and Cost Analysis of Accident Tolerant Plant Design based on Dynamic PRA Methodology
ATF and FLEX are expected to extend the existing LWRs' coping time and...
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NEUP CINR-18-15280: Advanced Alloy Innovations for Structural Components of Molten Salt Reactors
The goal of the proposed research is to develop and evaluate advanced...
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NEUP CINR-18-15307: A novel and flexible approach for converting LWR UNF fuel into forms that can be used to fuel a variety of Gen-IV reactors
We propose to investigate both the chemical decladding and the digestion of...
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NEUP CINR-18-15324: Validation of Pressure Relaxation Coefficient in RELAP-7 Seven-Equation Model
We aim at validating the seven-equation model in RELAP-7 by a combination of...
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NEUP CINR-18-15332: Low-Force Solid-State Technologies for Mitigation of Stress Corrosion Cracking in Dry Storage Canisters
The research involves the development of low force, low heat input solid...
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NEUP CINR-18-15345: Multiphysics degradation processes, and their mitigation, in engineered and geological barriers: experiments and simulation
The objective of the work is to understand the conditions, and to reduce the...
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NEUP CINR-18-15346: Big Data For Operation and Maintenance Cost Reduction
This research develops a first-of-a-kind framework to integrate Big Data...
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NEUP CINR-18-15372: Development of Repair and Mitigation Methods for Enhanced Stress Corrosion Cracking Resistance of Austenitic Stainless Steel Spent Nuclear Fuel Storage Canisters
The proposed research, which addresses work scope Id FC-4.2, will investigate...
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NEUP CINR-18-15381: Multiaxial Failure Envelopes and Uncertainty Quantification of Nuclear-Grade SiCf/SiC Woven Ceramic Matrix Tubular Composites
The Direct Micromechanics Method will be used to determine constitutive...
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NEUP CINR-18-15439: Radiolytic Dissolution Rate of Silicon Carbide
A major question regarding use of SiC/SiC composites as accident-tolerant LWR...
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NEUP CINR-18-15459: Reduced diffusion and enhanced retention of multiple radionuclides from pore structure studies of barrier materials for enhanced repository performance
The project will understand and quantify the pore structure and its emergent...
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NEUP CINR-18-15471: Integral Experimental Investigation of Radioisotope Retention in Flowing Lead for the Mechanistic Source Term Evaluation of Lead Cooled Fast Reactor
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NEUP CINR-18-15484: A novel high fidelity continuous-energy transport tool for efficient FHR transient calculations
The objective of the proposed project is to develop a novel high fidelity...
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NEUP CINR-18-15496: Formation of Zeolites Responsible for Waste Glass Rate Acceleration: An Experimental and Computational Study for Understanding Thermodynamic and Kinetic Processes
This project will elucidate the factors governing zeolite crystallization and...
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NEUP CINR-18-15502: Reducing Uncertainty in Radionuclide Transport Prediction Using Multiple Environmental Tracers
In this project, we will utilize direct modeling of multiple environmental...
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NEUP CINR-18-15520: Accurate and Efficient Parametric Model-Order Reduction for Turbulent Thermal Transport
This project will develop reduced-order models (ROMs) that will improve the...
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NEUP CINR-18-15531: Repair and Mitigation of Chloride-Induced Pitting and Chloride-Induced Stress Corrosion Cracking in Used Nuclear Fuel Dry Cask Canister Materials
This project will evaluate and develop a set of tools to repair and mitigate...
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NEUP CINR-18-15559: Cold Spray Repair & Mitigation of Stress Corrosion Cracks in Spent Nuclear Fuel Dry Storage Canisters
The objective of this project is to demonstrate cold spray repair and...
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