CASL

Science and Technology Archive

  • Lift Forces in Bubbly Flows

    The dynamics of two-phase (gas/liquid) bubbly flows are complex: bubbles deform and disperse; large latent heats and heat capacity differentials influence local boiling; and relatively small changes in heated surface temperatures yield order of magnitude changes in boiling complexity.

  • Validation of Peregrine with Test Reactor Data

    At the end of September, Pellet-Cladding Interaction (PCI) Challenge Problem Integrator Robert Montgomery reported that good progress has been made in demonstrating the Peregrine LWR fuel performance modeling software.

  • Implementing Integrated Steam Tables

    At the end of August, CASL published an equation of state model library for use with VERA. The IAPWS95 and IAPWS-IF97 standard models for the thermodynamic properties of water and the associated transport property models implemented within the library were verified to reproduce the analytic models across the range of validity.

  • Effect of Grain Boundaries on Irradiation Growth of Zirconium-based Alloys

    At the end of August, researchers S.I. Golubov, A.V. Barashev and R.E. Stoller delivered to CASL an analysis of the effect of grain size on the radiation growth of multigrain, hexagonal close-packed (hcp) metals, taking into account the features of cascade damage due to neutron exposure.

  • Pilot Project on Fibrous Debris Effects

    Pressurized water reactor (PWR) containment buildings are designed both to contain radioactive material releases and to facilitate core cooling in the event of a loss-of-coolant-accident (LOCA). Reactor core cooling following the LOCA may utilize water discharged from the LOCA pipe break and containment spray.

  • The Michigan Parallel Characteristics Transport Code

    MPACT (Michigan PArallel Characteristics Transport Code) is a new reactor analysis tool being developed at the University of Michigan as an advanced pin-resolved transport capability within VERA (Virtual Environment for Reactor Analysis).

  • 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.

  • 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.

  • 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.

  • 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.

  • 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.

  • CASL and TVA

    CASL and TVA, The Tennessee Valley Authority (TVA) provides operational experience and validation information to CASL.

  • 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.

  • 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.

  • 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.