Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis

J Wang, Q Wang, M Ding - Annals of Nuclear Energy, 2020 - Elsevier
In an operating nuclear reactor system, various physical phenomena of different properties
are intimately linked. These multiphysics phenomena include neutronics (N), thermal …

High-fidelity multi-physics coupling study on advanced heat pipe reactor

W Xiao, X Li, P Li, T Zhang, X Liu - Computer Physics Communications, 2022 - Elsevier
The advanced heat pipe cooled reactor is a potential candidate to generate nuclear power
for space exploration, and exhibits strong neutron leakage and complicated multi-physics …

Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square …

A Erfaninia, A Hedayat, SM Mirvakili… - Progress in Nuclear …, 2017 - Elsevier
The main purpose of this paper is neutronic-thermal hydraulics coupling analysis of the fuel
channel of an advanced Small Modular Reactor (SMR), which is nominated as a near term …

Numerical methods in coupled Monte Carlo and thermal-hydraulic calculations

DF Gill, DP Griesheimer, DL Aumiller - Nuclear Science and …, 2017 - Taylor & Francis
Large-scale reactor calculations with Monte Carlo (MC), including nonlinear feedback
effects, have become a reality in the course of the last decade. In particular, implementations …

CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor

R Henry, I Tiselj, L Snoj - Annals of Nuclear Energy, 2017 - Elsevier
A new computational model of the JSI TRIGA Mark II, coupling Monte Carlo neutron
transport code TRIPOLI and fluid dynamics code CFX was built and verified with a set of new …

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

MI Radaideh, T Kozlowski - International Journal of Energy …, 2019 - Wiley Online Library
A novel and modern framework for energy modeling is developed in this paper with a focus
on nuclear energy modeling and simulation. The framework combines multiphysics …

Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis

N García-Herranz, D Cuervo, A Sabater… - … Engineering and Design, 2017 - Elsevier
At UPM, in-depth modifications of the core simulator COBAYA, able to perform neutronics
diffusion calculations at both nodal and pin-by-pin levels, have been accomplished during …

[HTML][HTML] OFELIA: An OpenMC-FEniCSx coupling for neutronic calculation with temperature feedback

L Loi, S Riva, C Introini, F Giacobbo, X Wang… - … Engineering and Design, 2024 - Elsevier
The state of an operating nuclear reactor depends on several physical phenomena that
coexist and are interdependent: they can be taken into account simultaneously by adopting …

Uncertainty analysis of condensation heat transfer benchmark using CFD code GASFLOW-MPI

H Zhang, Y Li, J Xiao, T Jordan - Nuclear Engineering and Design, 2018 - Elsevier
With the development of the computational capability, Computational Fluid Dynamics (CFD)
is more and more widely used as the best estimate approach for the design and safety …

Improved design of LBE cooled solid reactor using 3D neutronics thermal-hydraulics coupling method

Q Yang, Q Pan, H He, T Zhang, X Liu - Annals of Nuclear Energy, 2022 - Elsevier
The goal of this study is to improve a micro reactor core into uniform power distribution, a
smaller and safer core. Neutronic thermal-hydraulics coupling is an effective means to study …