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Description of a stable scheme for steady-state coupled Monte Carlo–thermal–hydraulic calculations

Annals of Nuclear Energy, 2014
Abstract We provide a detailed description of a numerically stable and efficient coupling scheme for steady-state Monte Carlo neutronic calculations with thermal–hydraulic feedback. While we have previously derived and published the stochastic approximation based method for coupling the Monte Carlo criticality and thermal–hydraulic calculations, its ...
Jan Dufek, J. Eduard Hoogenboom
openaire   +2 more sources

Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal–hydraulic feedback

Annals of Nuclear Energy, 2013
Numerically stable Monte Carlo burnup calculations of nuclear fuel cycles are now possible with the previously derived Stochastic Implicit Euler method based coupling scheme. In this paper, we show that this scheme can be easily extended to include the thermal–hydraulic feedback during the Monte Carlo burnup simulations, while preserving its ...
Jan Dufek, Henryk Anglart
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DASSH: Software for ducted assembly thermal hydraulics calculations

Transactions of the American Nuclear Society, 2020
F. Heidet, M. Smith, M. Atz
openaire   +1 more source

ROBUSTNESS MAPS OF THE SYSTEM THERMAL HYDRAULIC CODE CALCULATION MODEL

Инновационные исследования в современном мире: сборник статей международной научной конференции (Санкт-Петербург, Июль 2026)
Предложен подход к количественной оценке робастности расчётной модели системного теплогидравлического кода в заданной области режимных и численных параметров. Приемлемость варианта определяется по совокупности условий завершения, физической допустимости, сохранения балансов массы и энергии и воспроизводимости.
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Procedure for calculation of thermal hydraulics of packed-bed core

Atomic Energy, 1992
V. P. Smirnov   +2 more
openaire   +1 more source

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   +1 more source

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