CASL’s Virtual Environment for Reactor Applications (VERA) prediction of the reactor coolant enthalpy distribution in a pressurized water reactor (PWR) at hot full power (left, 3D quarter-core; right, the plane at the exit of the core). Read More
An example of data transfer on a shared interface between two different spacer grid meshes using DTK. Most of VERA’s physics components utilize different mesh topologies to solve their part of the coupled problem and DTK is used to translate data between physics. Read More
The neutron density results from a VERA multiphysics 3D prediction of power, coolant temperature & density.
Bottom: Full core 2D fuel rod power using VERA’s MOC neutronics option at beginning of cycle (left), mid-cycle (center), and end of cycle (right). Top: a subregion view of the full core simulation.
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Coolant temperature distribution for the iPWR SMR simulated with ten control rod banks at each rod maneuver (degC). Read More
Snapshot of isosurfaces of the instantaneous phasic volume fraction near the spacer grid and mixing vanes in a 3x3 rod bundle. Read More
Flow patterns generated by spacer grid mixing vanes in a PWR fuel assembly (top) and a close up of view of the spacer grid geometry, with the mixing vanes and a fuel rod, used in the simulation. Read More
Turbulence structures generated by mixing vanes are visualized through helicity isosurfaces (above and right). Read More
Illustration of a nuclear reactor core: a quarter view of the CAD geometry (all but one fuel assembly removed for clarity) (left); a quarter view of the coolant temperature distribution during normal operation (center); and a half view of the reactor coolant pressure distribution (right). Read More
Under pressure, heat and radiation in the reactor environment, both the fuel pellets and the fuel rod cladding are affected at the microstructural level. These effects, among others, produce small changes in the fuel rod geometry that, on a cumulative basis, have the potential to influence the overall performance of the fuel rod and the reactor. Read More
Isosurfaces of the instantaneous streamwise drag in a two-phase flow for a 5x5 rod bundle between the reactor coolant and a dispersed bubble field. The effect of the spacer grid and mixing vanes on the drag distribution evident when the isosurfaces are examined. Read More
The Consortium for Advanced Simulation of Light Water Reactors (CASL) was established to provide leading edge modeling and simulation (M&S) capability to improve the performance of currently operating light water reactors. Our vision is safer and more productive commercial nuclear power production afforded through comprehensive science-based predictive M&S technology deployed and applied broadly by the U.S. nuclear energy industry. Towards that end, CASL is developing the Virtual Environment for Reactor Applications, VERA. CASL's VERA software simulates nuclear reactor physical phenomena using coupled multi-physics models. VERA's current physics capabilities include neutron transport, thermal-hydraulics, fuel performance, and coolant chemistry.
CRUD-Induced Power Shift (CIPS) Prediction Capability Demonstrated with VERADuring FY15, CASL significantly advanced VERA’s capability to model the CRUD Challenge Problem to predict the occurrence of CRUD Induced Power Shift (CIPS). VERA has been modified to include the space and time dependent deposition of CRUD onto the fuel, along with boron capture and its effects on local rod power and thermal hydraulic conditions. Early in CASL’s program, coolant chemistry subcomponents (MAMBA and MAMBA-BDM) were developed to describe local CRUD deposition. Since then the coolant chemistry subcomponents have been integrated within VERA’s subchannel thermal-hydraulics and neutronics subcomponents. Most recently all three subcomponents have been coupled within VERA, allowing VERA to simulate multiple cycles of operation to simulate CIPS. Read more
VERA Quick-Start, Lynchburg VA, December 15 & 16 (invitation only)
* Chatzikyriakou, D., J. Buongiorno, D. Caviezel and D. Lakehal, "DNS and LES of Turbulent Flow in a Closed Channel Featuring a Pattern of Hemispherical Roughness Elements," International Journal of Heat and Fluid Flow, Volume 53, pp. 29–43, June 6, 2015.
* Walsh, J.A., B. Forget, K.S. Smith and P.K. Romano, "Optimizations of the Energy Grid Search Algorithm in Continuous-energy Monte Carlo Particle Transport Codes," Computer Physics Communications, Elsevier, Volume Online, June 5, 2015.
* Larsen, E.W., and T.J. Trahan, "Asymptotic, Multigroup Flux Reconstruction and Consistent Discontinuity Factors," Journal of Nuclear Science and Technology, Issue Published online, May 12, 2015.
* Keady, K.P., and E.W. Larsen, Stability of Monte Carlo k-Eigenvalue Simulations with CMFD Feedback, CASL Technical Report: CASL-U-2015–0223–000, May 28, 2015.
* Stimpson, S.G., An Azimuthal, Fourier Moment-Based Axial SN Solver for the 2D/1D Scheme, CASL Technical Report: CASL-U-2015–0149–000, May 19, 2015.
* Adams, B.M., M.S. Ebeida, M.S. Eldred, J.D. Jakeman, L.P. Swiler, J.A. Stephens, D.M. Vigil, T.M. Wildey, W.J. Bohnhoff, K.R. Dalbey, J.P. Eddy, K.T. Hu, L.E. Bauman and P.D. Hough, DAKOTA: A Multilevel Parallel Object-Oriented Framework for Design Optimization, Parameter Estimation, Uncertainty Quantification, and Sensitivity Analysis: Version 6.2 Theory Manual, CASL Technical Report: CASL-U-2015–0090–000, May 8, 2015.
* Chatzikyriakou, D., J. Buongiorno, D. Caviezel and D. Lakehal, "DNS and LES Gehin, J.C., CASL Program Highlights June 2015, June 30, 2015, 2015.
* Chatzikyriakou, D., J. Buongiorno, D. Caviezel and D. Lakehal, "DNS and LES Adams, B., and V. Mousseau, Credible Simulation, Emphasizing Sensitivity, Uncertainty, and Calibration, 2015 CASL Student Workshop, June 19, 2015, Sandia National Laboratories, Albuquerque, New Mexico, 2015.
* Chatzikyriakou, D., J. Buongiorno, D. Caviezel and D. Lakehal, "DNS and LES Gehin, J.C., CASL Program Highlights May 2015, May 30, 2015, 2015.
CASL is the first United States Energy Innovation Hub established by the Department of Energy in 2010. CASL connects fundamental research and technology development through an integrated partnership of government, academia, and industry the extends across the nuclear energy enterprise. Read more about the CASL organization here.
