Coupled Monte Carlo and thermal-fluid modeling of high temperature gas reactors using Cardinal

AJ Novak, D Andrs, P Shriwise, J Fang, H Yuan… - Annals of Nuclear …, 2022 - Elsevier
Cardinal is an open-source application that couples OpenMC Monte Carlo transport and
NekRS computational fluid dynamics to the Multiphysics Object-Oriented Simulation …

Relaxation effects in nuclear fuel coupled calculations using serpent-OpenFOAM codes

T Korinek, J Zavorka, M Lovecky, R Skoda - Progress in Nuclear Energy, 2024 - Elsevier
Coupled multi-physics simulations play a crucial role in the design and operation of nuclear
reactors, particularly in assessing the behavior of used nuclear fuel. This study focuses on …

The virtual test bed (VTB) repository: a library of reference reactor models using NEAMS tools

GL Giudicelli, A Abou-Jaoude, AJ Novak… - Nuclear Science and …, 2023 - Taylor & Francis
With the next generation of nuclear reactors under development, modeling and simulation
tools are being developed by the US Department of Energy to support their design …

A hybrid domain overlap** method for coupling System Thermal Hydraulics and CFD codes

A Huxford, VC Leite, E Merzari, L Zou, V Petrov… - Annals of Nuclear …, 2023 - Elsevier
A hybrid multiscale coupling methodology based on a domain overlap** approach has
been developed for coupling System Thermal Hydraulics (STH) and Computational Fluid …

[PDF][PDF] Effect of heating configuration on plenum-to-plenum thermal hydraulics of buoyancy driven air

Z Zeitoun, MM Taha, IA Said, A Jasim… - Proceedings of …, 2023 - researchgate.net
Plenum-to-plenum thermal hydraulics in a Prismatic Modular Reactor (PMR) during loss of
flow accidents (LOFA) has been of high interest for several researchers. Accordingly, this …

The Verification, Validation and Application of a Hybrid Domain Overlap** Coupling between System Thermal Hydraulics and Computational Fluid Dynamics Codes

A Huxford - 2024 - deepblue.lib.umich.edu
One important problem in nuclear reactor safety analysis is how to compute the evolution of
accident events and accurately estimate reactor safety margins. Currently, regulatory …

Multi physics simulation on Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shock (PTS)

Y Yu, A Novak, D Shaver, E Merzari - 2022 - osti.gov
The structural components that comprise nuclear reactors and their supporting structures are
subjected to harsh operating environments that can challenge their integrity, especially after …

Measurement of the Reactivity Coefficients and Neutron Flux of the SLOWPOKE-2 Reactor Using OpenMC.

A El Mtili, O El Hajjaji, T El Bardouni… - International …, 2023 - search.ebscohost.com
This article aims to calculate and analyze the reactivity coefficients of a SLOWPOKE-2
reactor under different temperature conditions using the OpenMC code and two cross …

Status of New Models Hosted on the Virtual Test Bed (VTB) in 2022

The VTB hosts 20 distinct models, 8 of which were recently developed during 2022 and will
be discussed in more detail here. This article provides an overview of the various models …