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 …

[图书][B] Nuclear systems Volume II: Elements of thermal hydraulic design

NE Todreas, MS Kazimi, M Massoud - 2021 - taylorfrancis.com
This book provides advanced coverage of a wide variety of thermal fluid systems and
technologies in nuclear power plants, including discussions of the latest reactor designs and …

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

GH Yeoh - Experimental and Computational Multiphase Flow, 2019 - Springer
Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …

Recent advances in CFD simulations of multiphase flow processes with phase change

SJ Li, LT Zhu, XB Zhang, ZH Luo - Industrial & Engineering …, 2023 - ACS Publications
Phase change is a phenomenon that has been extensively utilized in chemical engineering,
energy, electronics, vehicle, and space exploration. From both the science and engineering …

[HTML][HTML] CFD simulation of an integrated PCM-based thermal energy storage within a nuclear power plant connected to a grid with constant or variable power demand

M Ali, AK Alkaabi, JI Lee - Nuclear Engineering and Design, 2022 - Elsevier
The current numerical study investigates the integration of a phase change material (PCM)-
based thermal energy storage (TES) system within a nuclear power plant (NPP) to enhance …

Latest research progress for LBE coolant reactor of China initiative accelerator driven system project

L Gu, X Su - Frontiers in Energy, 2021 - Springer
China's accelerator driven subcritical system (ADS) development has made significant
progress during the past decade. With the successful construction and operation of the …

[HTML][HTML] Drift-flux model for upward dispersed two-phase flows in vertical medium-to-large round tubes

T Hibiki, N Tsukamoto - Progress in Nuclear Energy, 2023 - Elsevier
The void fraction prediction is critical in nuclear safety analyses. Available one-dimensional
computational codes heavily depend on the two-fluid model. The interfacial drag force in the …

The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes

K Zhang - International Journal of Energy Research, 2020 - Wiley Online Library
Simulation is becoming increasingly important in the safety analysis of nuclear reactors
nowadays. The physical phenomena in a nuclear power plant happen on three classified …

[HTML][HTML] Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly

J Xiong, W Qu, T Zhang, X Chai, X Liu, Y Yang - Annals of Nuclear Energy, 2020 - Elsevier
In nuclear fuel assembly mixing vanes are fabricated on the spacer grids to promote
diversion cross flow and turbulent mixing. In order to investigate the decay of diversion cross …

Development of a flow sweeping mixing model for helical fuel rod bundles

Y Xiao, J Fu, Q Zhang, H Zhao, H Gu - Annals of Nuclear Energy, 2021 - Elsevier
The helical fuel rod is a kind of axially twisted fuel element with a three or four-petaled
profile. The helical fuel rod assembly assembled by helical fuel rods against one another in …