Projects
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NEUP CINR-25-34159: Advanced post-irradiation examination of accelerated burnup Cr-doped UO2
This project aims to uncover several outstanding questions in mechanistic...
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NEUP CINR-25-34188: Understanding neutron irradiation-assisted stress corrosion cracking mechanisms of 316L stainless steel made by laser additive manufacturing
The project studies the irradiation-assisted stress corrosion cracking...
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NEUP CINR-25-34204: Common Ground 2050: Public Engagement and Ambition as Preconditions for National Nuclear Readiness with Integrated Waste Management
The overall goal of this project is to advance use-inspired knowledge and...
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NEUP CINR-25-34211: Coupled Interface Capturing and Particle Tracking Methods for Fuel Dispersal Study During the Loss-of-Coolant Accident
The primary objective of the proposed research is to advance the predictive...
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NEUP CINR-25-34219: Development of an Efficient Impact Limiter for Transportation Casks
This research will develop impact limiters for transportation casks that...
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NEUP CINR-25-34230: A Comprehensive Uncertainty Quantification Methodology for High Fidelity Multi-Physics Simulation of Sodium-cooled Fast Reactors
The objective of this proposal is to develop a comprehensive uncertainty...
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NEUP CINR-25-34261: Integrating Graph Neural Operator with MOOSE Framework for Enhanced Transient Modeling and Real-Time Data Assimilation
We introduce the GNO-MOOSE hybrid solver, which combines Graph Neural...
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NEUP CINR-25-34280: A Multiphysics, Multi-Cycle Benchmark of the Fast Flux Test Facility (FFTF)
The Fast Flux Test Facility (FFTF) was a 400 MWth, MOX-fueled, sodium fast...
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NEUP CINR-25-34293: O&Mgpt: Context-Aware Natural Language Processing for Improving Operations and Maintenance Planning in Nuclear Power Plants
The goal of the proposed work is to develop O&Mgpt, a context-aware...
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NEUP CINR-25-34312: In situ ion irradiation mechanical testing to inform physics-based modeling of irradiation creep mechanisms in Grade 91
This project will study the impact of sequential vs. simultaneous irradiation...
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NEUP CINR-25-34353: Material Accountancy Evaluation of Plutonium Content from Beryllium Fuel Forms using New Nuclear Data Measurements of Be(alpha,n)-driven Be(n,2n) Reactions
The challenge of plutonium (Pu) quantification remains a persistent challenge...
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NEUP CINR-25-34364: Development and Characterization of (Semi-)Clathrate Hydrates for Capture and Separation of 85Kr and Xe from Nuclear Reactor Off-Gas Streams
The goal is to develop and characterize novel clathrate and semi-clathrate...
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NEUP CINR-25-34370: Robust and scalable cladding surfaces to enhance boiling heat transfer performance in LWR conditions
We propose to develop a robust and scalable method to increase boiling heat...
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NEUP CINR-25-34415: Compatibility studies of uranium nitride fuel with advanced cladding materials using multimodal diffusion experiments
Our goal is to use multiple designed diffusion experiments and multimodal...
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NEUP CINR-25-34429: Novel Nanostructured Coating Designs for Advanced Fuel Claddings Expedited by Modeling-Guided Approaches
The Purdue-UH-INL team propose to combine experimental and modeling...
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NEUP CINR-25-34435: Novel Lightweight Material for Spent Nuclear Fuel Transportation
This project aims to model, design, prototype and test high-strength and...
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NEUP CINR-25-34454: Multiscale assessment of claystone suitability for subsurface nuclear waste disposal
The goal of this project is identifying the properties of clay-rich...
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NEUP CINR-25-34511: Surface Complexation of Radionuclides on Mineral Surfaces at High Temperature
Adsorption models parameterized by adsorption constants are key to...
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NEUP CINR-25-34546: Physics-based Machine Learning Aided Multimodal NDT to Detect Internal Abnormalities in Sealed SNF Canisters
This project aims to develop a multimodal non-destructive testing (NDT)...
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NEUP CINR-25-34557: Characterization of film dryout on Silicon Carbide cladding with and without crud
The deposition of corrosion products (crud) on nuclear fuel cladding can...
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