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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
exaly   +2 more sources

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

The Effect of Variable Thermal Conductivity in Thermal-Hydraulic Calculations

Nuclear Technology, 1976
Many 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
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

Uncertainty and sensitivity analysis of a post-experiment calculation in thermal hydraulics

Reliability Engineering & System Safety, 1994
Abstract 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
openaire   +1 more source

Optimised Iteration in Coupled Monte Carlo – Thermal-Hydraulics Calculations

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
This 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
openaire   +1 more source

Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core

Nuclear Engineering and Design, 2002
The thermal hydraulic calculations of the 10 MW high temperature gas-cooled-test module (HTR-10) are among the most important indications to judge the reactor performance under design conditions. The power distribution, the temperature distribution and the flow distribution of the HTR-10 are calculated for initial and equilibrium core in this paper ...
Zuying Gao, Lei Shi
openaire   +1 more source

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   +1 more source

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