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Review of European Thermal-Hydraulic Calculational Methods for Thermal Reactors
Nuclear Science and Engineering, 1988During the past few years, there has been an increasing effort to understand the behavior of nuclear power plants (NPPs) in normal and abnormal situations. To achieve this goal, large computer codes that allow the description of two-phase flows with sources and sinks of mass and heat have been built in many countries.
M. A. Porracchia +2 more
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A CFD Method for Thermal-Hydraulic Calculation of Pebble Bed HTGRs
Volume 8: Computational Fluid Dynamics (CFD) and Applications, 2022Abstract 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
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Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations
Nuclear Science and Engineering, 2017Large-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
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The Effect of Variable Thermal Conductivity in Thermal-Hydraulic Calculations
Nuclear Technology, 1976Many thermal-hydraulic computer codes employ a fuel rod heat transfer model to couple the fuel rod temperatures with the hydraulic driving forces.
David A. Rehbein, Roger W. Carlson
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Thermal hydraulic preliminary calculations for small modular reactor based on ACPR50S technology
Ministry of Science and Technology, Vietnam, 2023This paper presents preliminary thermal-hydraulics calculation results for a small modular reactor (SMR) with a thermal capacity of 200 MW based on the ACPR50S reactor technology (Advanced customer-friendly practicable reliable 50 MWe compact SMR).
Dinh Hung Cao +3 more
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3D thermal-hydraulic calculations of a modular block-type HTR core
Nuclear Engineering and Design, 2006Abstract This paper deals with 3D numerical simulation of assemblies of a high temperature helium cooled reactor core. The present aim is to investigate an emergency situation due to the blocking of few Helium channels in the core. In this situation, some Helium channels for coolant passage are blocked and the related issue is the temperature ...
O. Cioni +3 more
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Calculation and analysis of thermal–hydraulics fluctuations in pressurized water reactors
Annals of Nuclear Energy, 2015Abstract Analysis of thermal–hydraulics fluctuations in pressurized water reactors (e.g., local and global temperature or density fluctuations, as well as primary and charging pumps fluctuations) has various applications in calculation or measurement of the core dynamical parameters (temperature or density reactivity coefficients) in addition to ...
Hessam Malmir, Naser Vosoughi
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Liquid-Metal-Cooled Reactor Thermal-Hydraulic Calculations in the United States
Nuclear Science and Engineering, 1988A wide range of thermal-hydraulic computer codes has been developed by various organizations in the United States. These codes cover an extensive range of purposes from within-assembly-wise pin temperature calculations to plantwide transient analysis. The codes are used for static analysis, analysis of protected anticipated transients, and analysis of ...
F. E. Dunn, D. J. Malloy, D. Mohr
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Steady state thermal hydraulic calculations for MTR plate-type research reactors
Kerntechnik, 2010Abstract A computation code THERMOHYD has been developed to perform the steady state thermal-hydraulic calculations of the MTR type research reactors fueled with plate-type-fuel, in the ranges of pressures and temperatures typical for MTR reactors.
I. D. Abdelrazek +3 more
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Optimization of AHWR core design: neutronics and thermal-hydraulics analysis and calculations
Life Cycle Reliability and Safety Engineering, 2020Advanced Heavy Water Reactor(AHWR) is being designed by BARC for thorium utilisation and demonstrate all aspects of the thorium fuel cycle. The AHWR is a vertical pressure tube type thorium-based reactor cooled by boiling light water and moderated by heavy water. The equilibrium fuel cycle of AHWR is being optimised for a discharge burn-up of 40 GWd/Te
Vishal Bharti +8 more
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