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A CFD Method for Thermal-Hydraulic Calculation of Pebble Bed HTGRs

Volume 8: Computational Fluid Dynamics (CFD) and Applications, 2022
Abstract The high temperature gas-cooled reactor (HTGR) is an advanced reactor type with safety characteristics of Generation IV nuclear energy systems. In the design process of an HTGR, thermal-hydraulic analysis is of great significance.
Junbing Zhu, Fubing Chen
openaire   +2 more sources

A Single Channel Thermal-Hydraulic Calculation Module for PWR Pin-by-Pin Wise Coupled Calculation System

Volume 6: Thermal-Hydraulics and Safety Analysis
Abstract Due to the strong feedback effect between neutronics and thermal-hydraulics in the core of pressurized water reactors (PWR), neutronics and thermal-hydraulics coupling calculations are often used in the design and safety evaluation of PWR to provide more accurate results.
Zhigang Li   +5 more
openaire   +2 more sources

Improving Thermal-Hydraulic Calculation Modules of THERMIX Code Based on LU Decomposition

Volume 4: Thermal Hydraulics, 2013
THERMIX is a software package for analyzing the thermal-hydraulic and safety behavior of pebble-bed high temperature gas-cooled reactor under both normal condition and accident conditions. The point-wise iterative solution method of THERMIX is time-consuming and difficult to be extended.
Yang Tang, Yangping Zhou, Zhiwei Zhou
openaire   +2 more sources

Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations

Nuclear Science and Engineering, 2017
Large-scale reactor calculations with Monte Carlo (MC), including nonlinear feedback effects, have become a reality in the course of the last decade.
Daniel F. Gill   +2 more
openaire   +2 more sources

Analysis and Improvement of Flow Field Calculation in Thermal Hydraulic Program for High Temperature Gas-Cooled Reactor

Volume 15: Student Paper Competition, 2022
The flow field calculation plays a crucial role in thermal-hydraulic calculation of High Temperature Gas-cooled Reactor (HTGR). While using the thermal-hydraulic program for HTGR to calculate the low-flow condition, the calculation of the helium ...
Dou Haoming   +3 more
semanticscholar   +1 more source

A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD

Nuclear science and engineering, 2023
Molten salt nuclear reactors (MSRs) constitute a promising technology to produce safe, reliable, abundant low-carbon energy. To design MSR systems and perform safety analyses on them, numerical simulation is a powerful tool.
Nathan Greiner   +4 more
semanticscholar   +1 more source

Calculation Method for Thermal-Hydraulic System Simulation

Journal of Heat Transfer, 2008
This paper presents the fundamental approaches of modeling thermal-hydraulic component briefly. A set of lumped parameter mathematical models is developed, which are based on conservation of mass and energy. Subsequently, the connection rule for basic thermal-hydraulic components and the method to automatically generate the complete thermal-hydraulic ...
Li Chenggong, Jiao Zongxia
openaire   +1 more source

High-Fidelity Coupled Monte-Carlo/Thermal-Hydraulics Calculations

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
Monte Carlo methods have been used as reference reactor physics calculation tools worldwide. The advance in computer technology allows the calculation of detailed flux distributions in both space and energy. In most of the cases however, those calculations are done under the assumption of homogeneous material density and temperature distributions.
Aleksandar Ivanov   +2 more
openaire   +2 more sources

Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET

Nuclear Science and Techniques, 2022
Yan-Ling Zhu   +4 more
openaire   +2 more sources

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