Y Wu, B Liu, H Zhang, K Zhu, B Kong, J Guo… - Annals of Nuclear Energy, 2021 - Elsevier
Abstract The Helical coiled tube Once-Through Steam Generator (H-OTSG) is key equipment in the High-Temperature Gas-cooled Reactor (HTGR) system, where the fission …
N Ahmed, S Singh, N Kumar - International Journal for …, 2024 - Wiley Online Library
The nodal integral methods (NIMs) have found widespread use in the nuclear industry for neutron transport problems due to their high accuracy. However, despite considerable …
Y Niu, Y He, F Xiang, J Zhang, Y Wu, W Tian… - Annals of Nuclear …, 2021 - Elsevier
Traditional reactor system analysis tools are confronted with challenging difficulties in model development, low accuracy, and poor convergence. To solve these problems, the automatic …
L Zou, H Zhao, H Zhang - Nuclear Engineering and Design, 2016 - Elsevier
This work represents a first-of-its-kind successful application to employ advanced numerical methods in solving realistic two-phase flow problems with two-fluid six-equation two-phase …
H Esmaili, H Kazeminejad, H Khalafi… - Annals of Nuclear …, 2020 - Elsevier
In this paper, a numerical procedure for thermal–hydraulic subchannel analysis of the annular fuel assembly in a PWR using the drift-flux model (DFM) is presented. The system of …
J Fan, J Gou, J Huang, J Shan - International Journal for …, 2023 - Wiley Online Library
Abstract Jacobian‐Free Newton–Krylov (JFNK) method is a stable and high‐efficiency method to solve the multi‐physics coupling problem for the modeling and simulation (M&S) …
Stencil computations are widely used to simulate the change of state of physical systems across a multidimensional grid over multiple timesteps. The state-of-the-art techniques in …
L Zou, H Zhao, H Zhang - Annals of Nuclear Energy, 2015 - Elsevier
The majority of the existing reactor system analysis codes were developed using low-order numerical schemes in both space and time. In many nuclear thermal–hydraulics …