Projects
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NEUP CINR-18-15578: Computational and Experimental Investigation of Thermal-Mechanical- Chemical Mechanisms of High-burnup Spent Nuclear Fuel (SNF) Processes at Elevated Temperatures and Degradation Behavior in Geologic Repositories
The overarching goal of the combined computational and experimental R&D...
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NEUP CINR-18-15585: Impact of coupled gas migration and thermo-hydro-mechanical processes on the performance of repositories for high level nuclear waste
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NEUP CINR-18-15596: Capture of Organic Iodides from Vessel Off-Gas Streams
The capture of radioactive organo iodides from off gas streams produced...
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NEUP CINR-18-15602: Modeling and Experimental Verification of Thermal Energy Storage Systems to Enable Load Following Capability for Nuclear Reactors
The proposed work aims at integrating new thermal energy storage (TES) models...
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NEUP CINR-18-15649: Benchmarking Microscale Ductility Measurements
The objectives of the proposed study are 1) to establish best practices for...
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NEUP CINR-18-15701: Time-dependent THMC properties and microstructural evolution of damage rocks in excavation damage zone
This project delineates an integrated experimental, theoretical and numerical...
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NEUP CINR-18-15703: Bridging microscale to macroscale mechanical property measurements and predication of performance limitation for FeCrAl alloys under extreme reactor applications
The project involves ion irradiation and deformation to introduce defects of...
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NEUP CINR-18-15733: Development of Multi-Axial Failure Criteria for Nuclear Grade SiCf-SiCm Composites
This project will conduct experiments and modeling work to help establish...
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NEUP CINR-18-15773: Evaluation of the Thermal Scattering Law for Advanced Reactor Neutron Moderators and Reflectors
The objective of this project is to narrow the nuclear data gap for advanced...
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NEUP CINR-19-16297: Irradiation studies on electron beam welded PM-HIP pressure vessel steel
The objective of this project is to assess the integrity of electron beam...
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NEUP CINR-19-16298: I-PRA Decision-Making Algorithm and Computational Platform to Develop Safe and Cost-Effective Strategies for the Deployment of New Technologies
This project develops an I-PRA Decision-Making Algorithm to support risk-and-...
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NEUP CINR-19-16380: High Fluence Active Irradiation and Combined Effects Testing of Sapphire Optical Fiber Distributed Temperature Sensors
This project will test and characterize distributed temperature measurements...
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NEUP CINR-19-16391: GuArDIAN: General Active Sensing for conDItion AssessmeNt
The goal of this project is the development of a dependable, autonomous or...
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NEUP CINR-19-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT
The objective of this project is to determine irradiated U-Pu-Zr fuel thermal...
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NEUP CINR-19-16567: Irradiation-assisted Stress Corrosion Cracking of PWR-irradiated Type 347 Stainless Steel
This project will use material from commercial pressurized water reactor...
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NEUP CINR-19-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF
The team will perform a systematic diffusion study on both neutron-irradiated...
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NEUP CINR-19-16739: IMPROVEMENTS OF NUCLEAR DATA EVALUATIONS FOR LEAD ISOTOPES IN SUPPORT OF NEXT GENERATION LEAD-COOLED FAST SYSTEMS
Modern design and licensing practices requires accurate simulation and...
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NEUP CINR-19-16743: Paths Forward for Nuclear Energy: Using a Nationwide Post-Stratified Hierarchical Model to Facilitate Matching of New Nuclear Technologies to Receptive Host Communities
This project will enable deployment of advanced nuclear technologies by...
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NEUP CINR-19-16754: Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis
To date no single alloy has satisfied all requirements of LFR/LBEFR...
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NEUP CINR-19-16790: Context-Aware Safety Information Display for Nuclear Field Workers
The overall goal of this project is to test the hypothesis that introducing...
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