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Optimised Iteration in Coupled Monte Carlo – Thermal-Hydraulics Calculations
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014This paper describes an optimised iteration scheme for the number of neutron histories and the relaxation factor in successive iterations of coupled Monte Carlo and thermal-hydraulic reactor calculations based on the stochastic iteration method.
J. Eduard Hoogenboom, Jan Dufek
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Athena Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment with RELAP5 Code
Journal of Nuclear Engineering and Radiation Science, 2023Among the envisaged experimental infrastructures supporting ALFRED reactor development, FALCON consortium identified ATHENA as one of the facilities to address the pool thermal-hydraulic challenges and demonstrate the feasibility of the revised ALFRED ...
T. Del Moro +6 more
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Coulped neutronics/thermal-hydraulics calculation of VVER-1000 fuel assembly
Nuclear Science and Technology, 2016This paper presents a computational scheme using MCNP5 and COBRA-EN for coupling neutronics/thermal hydraulics calculation of a VVER-1000 fuel assembly. A master program was written using the PERL script language to build the corresponding inputs for the MCNP5 and COBRA-EN calculations and to manage the coupling scheme.
Duy Long Ta +4 more
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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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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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