Results 271 to 280 of about 56,882 (308)
Some of the next articles are maybe not open access.
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
openaire +1 more source
Description of a stable scheme for steady-state coupled Monte Carlo–thermal–hydraulic calculations
Annals of Nuclear Energy, 2014Abstract 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
Coupling of the thermal-hydraulic and neutronic calculations for bwrs
202011 ÖZET Kaynar Su Reaktörlerde termal-hidrolik ve nötronik hesaplar arasında kuvvetli bir bağlaşım bulunur. Bir Kaynar Su Reaktörüne bu bağlaşım hesaplarını uygulamak için COBRA-IV bilgisayar kodu alt-kanal analizinde, WIMS-D/4 kodu makroskopik etkin tesir kesiti hesaplarında ve CITATION kodu asemble ve kor güç hesaplarında kullanılmıştır.
openaire +1 more source
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
openaire +2 more sources
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
openaire +2 more sources
Influence of Thermal-Hydraulic Model to Fuel Management Core Calculation
2008The integration of neutronic, fuel rod and thermal-hydraulic calculations for both, steady-state core design type of the calculation and for transient and safety analyses, is used to improve the response of Nuclear Power Plants (NPP) both from the point of view of safe and economic plant operation.
Iveković, Ilijana +2 more
openaire +2 more sources
Quantitative assessment of thermal–hydraulic codes used for heavy water reactor calculations
Nuclear Engineering and Design, 2006Abstract The RD-14M large LOCA test, characterized by a reliable set of experimental data, was selected for an international standard problem exercise (SPE) entitled “Intercomparison and validation of computer codes for thermal–hydraulics safety analyses”.
Andrej Prošek +3 more
openaire +1 more source
DASSH: Software for ducted assembly thermal hydraulics calculations
Transactions of the American Nuclear Society - Volume 123, 2020F. Heidet, M. Smith, M. Atz
openaire +1 more source
Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET
Nuclear Science and Techniques, 2022Yan-Ling Zhu +4 more
openaire +1 more source
Procedure for calculation of thermal hydraulics of packed-bed core
Atomic Energy, 1992V. P. Smirnov +2 more
openaire +1 more source
Nuclear Technology, 2019
AbstractPredictive Modeling Methodology constitutes an innovative approach to perform uncertainty analysis (UA) that reduces the subjective and user-defined ways to manage experimental data and der...
openaire +1 more source
AbstractPredictive Modeling Methodology constitutes an innovative approach to perform uncertainty analysis (UA) that reduces the subjective and user-defined ways to manage experimental data and der...
openaire +1 more source