467 results on '"Merzari, Elia"'
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52. Neutron Source Facility of the National Science Center “Kharkiv Institute of Physics and Technology” at Kharkiv, Ukraine
53. Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor Downcomer Geometry
54. Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry
55. Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment
56. Development of a Benchmark for Thermal Striping in Gas-Cooled Fast Reactors
57. Toward Improved Correlations for Mixed Convection in the Downcomer of Molten Salt Reactors
58. Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics
59. Direct Numerical Simulation of Heat Transfer in a 7-Pin Wire-Wrapped Rod Bundle
60. Updates to Nek5000: RANS wall functions, NRC support, and documentation
61. CFD Simulations to Support Pronghorn Modeling of a Molten Salt Fast Reactor
62. Evaluation of hot channel factor for sodium-cooled fast reactors with multi-physics toolkit
63. Wall resolved large eddy simulation of reactor core flows with the spectral element method
64. On the relevance of turbulent structures resolution for cross-flow in a helical-coil tube bundle
65. Verification and validation of large eddy simulation with Nek5000 for cold leg mixing benchmark
66. Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing
67. One-way coupled simulation of FIV in a 7-pin wire-wrapped fuel pin bundle
68. Foreword
69. Exascale Multiphysics Nuclear Reactor Simulations for Advanced Designs
70. Frontier: Exploring Exascale
71. A more open future for nuclear science and technology
72. Direct Numerical Simulation of Heat Transfer in a 7-Pin Wire-Wrapped Rod Bundle
73. Multi physics simulation on Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shock (PTS) by using Cardinal
74. Challenge Problem 1: Preliminary Model Development and Assessment of Flexible Heat Transfer Modeling Approaches
75. Multi physics simulation on Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shock (PTS)
76. Spectral and modal analysis of the flow in a helical coil steam generator experiment with large eddy simulation
77. High fidelity simulation and validation of crossflow through a tube bundle and the onset of vibration
78. Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly
79. On the use of LES-based turbulent thermal-stress models for rod bundle simulations
80. Invariant analysis of the Reynolds stress tensor for a nuclear fuel assembly with spacer grid and split type vanes
81. Sensitivity analyses in a buoyancy-driven closed system with high resolution CFD using Boussinesq approximation and variable density models
82. A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes
83. Foreword: Selected papers from the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)
84. Selected papers from the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)
85. Large Eddy Simulation of Convective Heat Transfer in a Random Pebble Bed Using the Spectral Element Method
86. Toward Improved Correlations for Mixed Convection in the Downcomer of Molten Salt Reactors
87. Transitional and Turbulent Bent Pipes
88. PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle
89. Port and optimize the CEED software stack to Aurora/Frontier EA (ECP Milestone Report)
90. Initial use of Nek5000/Cardinal to improve closure models in Pronghorn
91. Flow-induced vibration analysis of a helical coil steam generator experiment using large eddy simulation
92. Numerical simulations for determination of minimum representative bundle size in wire wrapped tube bundles
93. A performance analysis of ensemble averaging for high fidelity turbulence simulations at the strong scaling limit
94. Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry
95. High-Fidelity Simulation of Mixing Phenomena in Large Enclosures
96. Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics
97. High-Fidelity Modeling and Experiments to Inform Safety Analysis Codes for Heat Pipe Microreactors
98. Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor
99. Demonstration of CFD to support the coupled analysis of a reactor pressure vessel subjected to pressurized thermal shock
100. Challenge Problem 1: Benchmark Specifications for the Direct Numerical Simulation of Canonical Flows
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