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Research on Interface Technology of Coupling Thermal-Hydraulics and Other Codes
With the rapid improvement of computer performance and solving algorithms, the high-precision simulation of nuclear power plant becomes more and more...
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Multi-Physics Coupling Model for Thermal Hydraulics and Solute Transport in CRUD Deposits
The porous Chalk River Unidentified Deposit (CRUD) depositions on the fuel cladding have a great impact on the heat transfer and power distribution...
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Neutronics and Thermal-Hydraulics Coupling Analysis of Integral Inherently Safe Fluoride-Salt-Cooled High-Temperature Advanced Reactor - Fustar
The integral inherently safe fluoride salt cooled high-temperature advanced reactor – FuSTAR is designed by **’an Jiaotong University with the...
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Development and Preliminary Verification of a Neutronics-Thermal Hydraulics Coupling Code for Research Reactors with Unstructured Meshes
To maximize their adaptability and versatility, research reactors are designed to adapt to various operational conditions. These requirements result...
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Fundamental and Applied Investigations of Thermal Hydraulics for Fast Reactors with Liquid-Metal Coolants
AbstractThe results of investigations in the field of hydrodynamics and heat transfer in fast reactors and an accelerator-controlled system with...
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Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor
Among the six advanced reactor systems identified by the Generation IV International Forum, the lead fast reactor (LFR) has been considered as one of...
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ASTEC Simulation of Dust Resuspension Behavior Induced by LOCA in Fusion Reactors
Dust resuspension behavior is critical to fusion reactors during an in-vessel loss of coolant accident (LOCA), since it may threaten the integrity of...
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Multi-physics Coupling Analyses of Nuclear Thermal Propulsion Reactor
Nuclear thermal propulsion (NTP) reactors have high-temperature solid-state characteristics and significant thermal expansion, which therefore...
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Preliminary safety analysis for a heavy water-moderated molten salt reactor
The heavy water-moderated molten salt reactor (HWMSR) is a newly proposed reactor concept, in which heavy water is adopted as the moderator and...
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Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET
To perform nuclear reactor simulations in a more realistic manner, the coupling scheme between neutronics and thermal-hydraulics was implemented in...
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An improved analysis method for assessing the nuclear-heating impact on the stability of toroidal field magnets in fusion reactors
The superconducting magnet system of a fusion reactor plays a vital role in plasma confinement, a process that can be disrupted by various...
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Coupled Neutronics and Thermal-Fluid Calculation for Prismatic High-Temperature Gas-Cooled Reactor Core at Steady State
With the rapid development of high-performance computers, high-precision, multi-scale and multi-physics coupling has become one of the main research...
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Verification of Solver for Coupled Simulation of Fluid and Fuel Pin in LFR Based on Openfoam
The Computational Fluid Dynamics (CFD)-based thermal-hydraulics and safety analyses of Lead-based Fast Reactor (LFR) have attracted great attentions...
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Monte Carlo simulations of the SPERT III E-core transient experiments
We perform simulations of two reactivity-insertion experiments in the SPERT III E-core nuclear research reactor. The simulations use the TRIPOLI-4 ® ...
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Flow field effect of delayed neutron precursors in liquid-fueled molten salt reactors
In molten salt reactors (MSRs), the liquid fuel salt circulates through the primary loop and a part of the delayed neutron precursors (DNPs) decays...
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Transient Behaviors of Thermo-Hydraulic and Thermal Stratification in the Pressurizer Surgeline for the Nuclear Power Plant
In pressurized water reactor (PWR) system, the surgeline plays an important role in bonding the pressurizer and the primary circle. Some considerable...
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A high fidelity general purpose 3-D Monte Carlo particle transport program JMCT3.0
JMCT is a large-scale, high-fidelity, three-dimensional general neutron–photon–electron–proton transport Monte Carlo software system. It was...
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A Serpent/OpenFOAM coupling for 3D burnup analysis
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuclear systems through the coupling between...
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Summary, Conclusion and Outlook
To quantify the output uncertainty, the concept of tolerance limits was applied. This technique reduced the number of runs to 93, which was...
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Introduction
In today’s industries (e.g. nuclear power industry, aerospace industry), there are various systems operating in a wide range of regimes. Since it is...