Results 271 to 280 of about 104,473 (310)
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Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback
Annals of Nuclear Energy, 2015Abstract The Monte Carlo method provides the most accurate description of the particle transport problem. The criticality problem is simulated by following the histories of individual particles without approximating the energy, angle or the coordinate dependence. These calculations are usually done using homogeneous thermal hydraulic conditions. This
Ivanov, A. +3 more
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Neutronics and Thermal Hydraulics Coupled 3-D Calculation of Pressure-Tube Deformation
Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, 2020Abstract Among the various parts in a pressurized heavy-water reactor (PHWR), pressure tubes are of tremendous importance. This is because they withstand extreme both pressure and temperature differences that exist between the Primary Heat Transport System (PHTS) and the moderator.
Eunhyun Ryu +3 more
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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
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Improving Thermal-Hydraulic Calculation Modules of THERMIX Code Based on LU Decomposition
Volume 4: Thermal Hydraulics, 2013THERMIX is a software package for analyzing the thermal-hydraulic and safety behavior of pebble-bed high temperature gas-cooled reactor under both normal condition and accident conditions. The point-wise iterative solution method of THERMIX is time-consuming and difficult to be extended.
Yang Tang, Yangping Zhou, Zhiwei Zhou
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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
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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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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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DASSH: Software for ducted assembly thermal hydraulics calculations
Transactions of the American Nuclear Society - Volume 123, 2020F. Heidet, M. Smith, M. Atz
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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
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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
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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.
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