Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM

X Liu, K Liu, M Wang, C Chen, Q Lu, W Tian… - Progress in Nuclear …, 2023 - Elsevier
In this paper, a full scale three-dimensional thermal-hydraulic analysis method for plate-type
fuel reactor core is proposed through integrating traditional sub-channel analysis concepts …

Steady-state and transient simulations of the MTR research reactor using the high-fidelity N-TH coupling method

Q **e, X Chai, X Liu - Progress in Nuclear Energy, 2023 - Elsevier
The tremendous advancement in computer technology makes it feasible to perform high-
fidelity and multi-physics numerical simulations of reactors, allowing for a more accurate and …

Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor

G Wang, Z Yue, R Sun, D Li, X Liu, B Wang… - Annals of Nuclear …, 2022 - Elsevier
Deep pool nuclear reactor (DPNR) is a novel pool-type reactor, which has shown great
potential in seawater desalination and district heating. In this paper, the thermal–hydraulic …

Plate spent fuel burnup measurement equipment based on a compact DD neutron generator

YN Li, Z Wei, GT Gao, L Wu, K Wu, J Ma, XY Liu… - Nuclear Science and …, 2025 - Springer
Burnup measurement is crucial for the management and disposal of spent fuel. The
conventional approach indirectly estimates burnup by examining the fission product or …

CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core

S Dibyo, W Luthfi, S Pinem, ID Irianto… - Acta Polytechnica, 2022 - ojs.cvut.cz
A nuclear reactor cooling system that has been operating for a long time can carry some
debris into a fuel coolant channel, which can result in a blockage. An in-depth two …

Transient analyses of the Jordanian 5 MW research reactor under LOEP accident

OS Al-Yahia, H Lee, D Jo - Annals of Nuclear Energy, 2016 - Elsevier
The Jordanian 5 MW research reactor is simulated to investigate its transient behavior under
a Loss Of Electric Power (LOEP) accident. The reactor cooling system is under downward …

A two-phase model for simulation of MTR type research reactor during protected and unprotected LOFA

S Talebi, P Najafi - Progress in Nuclear Energy, 2019 - Elsevier
An optimized, accurate and fast model is investigated to simulate the transient behavior of a
research reactor during fast and slow LOFA (loss of flow accident). Simulation is performed …

Research on burnup depth measurement of spent fuel board based on thermal neutron imaging technology

G Gao, Z Chen, G Wan, Z Wei, X Liu, Y Li… - Journal of …, 2024 - iopscience.iop.org
The detection equipment for measuring the burnup depth in spent fuel rods is a vital
component of the spent fuel management system. which can determine the burnup depth of …

Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1

ERGD Ribeiro, DAP Palma, E Henrice Jr, J Su - Annals of Nuclear Energy, 2020 - Elsevier
Dynamical behavior of the Brazilian Multipurpose Reactor (RMB) is investigated by using
the coupled neutronics and thermal hydraulics code NTHC1, which consists of the neutron …

Loss Of Flow Accident (LOFA) with protection in NUR nuclear research reactor; three dimensional analysis of a Fast LOFA and a Slow LOFA

N Akhal, K Sidi-Ali, S Benmamar - Progress in Nuclear Energy, 2023 - Elsevier
Abstract The Loss Of Flow Accident (LOFA), with protection and without intervention of
natural convection in the cooling process, is studied in the NUR nuclear research reactor for …