Results 261 to 270 of about 105,023 (307)
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High-Fidelity Coupled Monte-Carlo/Thermal-Hydraulics Calculations
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014Monte 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
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Uncertainty and sensitivity analysis of a post-experiment calculation in thermal hydraulics
Reliability Engineering & System Safety, 1994Abstract This uncertainty and sensitivity analysis accounts for modeling and parameter uncertainties originating from the experiment, the mathematical model, and the numerical solution algorithm. Quantitative uncertainty statements are derived for code results that are either single-value quantities, like the peak cladding temperature, or continuous-
H. Glaeser +3 more
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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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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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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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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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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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Introducing and validating a new method for coupling neutronic and thermal-hydraulic calculations
Nuclear Engineering and Design, 2010Abstract In this study, a new and innovative method is introduced for analyzing neutronic and thermal-hydraulic calculation. For this aim, VVR-S research reactor was selected, and the calculation procedure was performed for it. WIMS, CITATION and COBRA-EN codes were used for investigation.
Nafiseh Zare +4 more
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Thermal Engineering, 2019
The results from experimental investigation into hydrodynamics and heat transfer in a two-phase natural circulation loop (NCL) under atmospheric pressure are presented. The experiments were carried out for liquids having essentially different properties: water, ethanol, and perfluorohexane C6F14 (the product trademark is FC-72).
V. V. Yagov +3 more
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The results from experimental investigation into hydrodynamics and heat transfer in a two-phase natural circulation loop (NCL) under atmospheric pressure are presented. The experiments were carried out for liquids having essentially different properties: water, ethanol, and perfluorohexane C6F14 (the product trademark is FC-72).
V. V. Yagov +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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