Analysis of molecular-level fracture and stress mechanisms could have broad implications for understanding materials’ behavior.
Research & Development
Science and Technology Archive
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Probing the mysteries of cracks and stresses
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Public Release of CASL Infrastructure Software
The Virtual Environment for Reactor Applications (VERA) comprises a suite of tools for scalable simulation of nuclear reactor core behavior.
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Nuclear Energy - Supercomputer speeds path forward
When run on graphics processing units, Denovo ran 3.5 times faster than what was possible with ORNL's Jaguar, which uses only central processing units.
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Initial Validation and Benchmark Study of new 3D CRUD Model
A new 3D CRUD model, known as "MAMBA" (for “MPO Advanced Model for Boron Analysis”), is being developed by the Crud Group within the MPO focus area of CASL.
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Radiation Transport Methods Update
The Radiation Transport Methods (RTM) focus area is responsible for the development of methods, algorithms, and implementations of radiation transport methods as they apply to the design and analysis of light water nuclear reactors.
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Keeping It Real
To ensure its modeling and simulation research activities are appropriately focused on specific industry issues, CASL engages an Industry Council chaired by the Electric Power Research Institute.
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Public Release of CASL Infrastructure Software
The Lightweight Integrating Multiphysics Environment (LIME), which has formed the infrastructure for the simulation tools being developed within the Consortium for Advanced Simulation of Light-Water Reactors (CASL), has been publicly-released under an open-source license.
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Modeling the Future of Nuclear Energy
NC State researchers use advanced computer simulations to create safer, more cost-effective nuclear power plants.
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Materials and Performance Optimization (MPO)
The Materials and Performance Optimization (MPO) focus area within CASL has recently developed and released a 3D modeling framework known as MAMBA (MPO Advanced Model for Boron Analysis) to predict CRUD deposition on nuclear fuel rods. CRUD, which refers to Chalk River Unidentified Deposit, is predominately a nickel-ferrite spinel corrosion product that deposits on hot fuel clad surfaces in nuclear reactors.
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PWR Reactor Vessel Multi-Physics CFD Model
A complete 3D SolidWorks CAD model of Watts Bar Unit 1 was constructed based on drawings. A single fuel assembly CAD model including all geometrical details was created based on the Westinghouse V5H 17x17 fuel design.
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CASL and TVA
CASL and TVA, The Tennessee Valley Authority (TVA) provides operational experience and validation information to CASL.
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Industry Council and CASL Project are Engaged to Investigate Workflow Processes to Ensure Value and Usability of CASL Results
CASL Thermal Hydraulics team had a considerable presence at the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics that took place in Toronto from Sept. 25-30, 2011. The NURETH series of conferences is an outstanding international technical forum on different topics related to thermalhydraulics and nuclear reactor safety with participation from leading practitioners and academic and industry researchers from around the world.
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CASL’s presence at Nureth-14
CASL Thermal Hydraulics team had a considerable presence at the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics that took place in Toronto from Sept. 25-30, 2011. The NURETH series of conferences is an outstanding international technical forum on different topics related to thermalhydraulics and nuclear reactor safety with participation from leading practitioners and academic and industry researchers from around the world.
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JOM: The Member Journal of TMS
CASL-MPO team members served as guest editors for vol 63, issue 8 of JOM (Journal of TMS, the Minerals, Metal and Materials Society) dedicated to Advanced Fuel Performance: Modeling and Simulation.
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Successful expanded prediction of the nature of CRUD found in pressurized water reactor coolant
Currently, the EPRI/WEC (Electric Power Research Institute/Westinghouse Electric Company) simulation capability (known as "BOA") for CRUD analysis only considers uptake of boron (present in the coolant of pressurized water reactors) into CRUD layers via the compounds lithium metaborate (LiBO2) or lithium tetraborate (Li2B4O7).