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Assessment of Subchannel Code ASSERT-PV for Flow-Distribution Predictions
Volume 4: Thermal Hydraulics, 2013The recently released ASSERT-PV 3.2 code version provides improvements in the predictions of flow distribution, critical heat flux (CHF) and dryout power, and post-dryout (PDO) fuel sheath temperatures. This paper summarizes the flow distribution prediction improvements achieved with the new code version, by comparing code predictions against ...
A. Nava-Dominguez +2 more
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Numerical method improvement for a subchannel code
Kerntechnik, 2016Abstract Previous studies showed that the subchannel codes need most CPU time to solve the matrix formed by the conservation equations. Traditional matrix solving method such as Gaussian elimination method and Gaussian-Seidel iteration method cannot meet the requirement of the computational efficiency.
W. J. Ding, J. L. Gou, J. Q. Shan
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The effect of turbulent mixing models on the predictions of subchannel codes
Nuclear Engineering and Design, 1994Abstract In this paper, the predictions of the COBRA-IV and ASSERT-4 subchannel codes have been compared with experimental data on void fraction, mass flow rate, and pressure drop obtained for two interconnected subchannels. COBRA-IV is based on a one-dimensional separated flow model with the turbulent intersubchannel mixing formulated as an ...
A. Tapucu +3 more
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The Principle and Preliminary Validation of a New Subchannel Code
Volume 4: Thermal Hydraulics, 2013Following China’s road map of nuclear technology development, the development of self-reliant nuclear design codes becomes one of the most significant steps in the plan. Among the nuclear design codes, thermal-hydraulic analysis code is indispensable because it is the foundation of reactor safety analysis and reactor design.
Ning Bai +7 more
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On the use of RELAP5-3D as a subchannel analysis code
Nuclear Engineering and Design, 2010Abstract The capabilities of the RELAP5-3D code to perform subchannel analyses in sodium-cooled fuel assemblies were evaluated. The motivation was the desire to analyze fuel assemblies with traditional (solid pins) as well as non-traditional (e.g., annular pins with internal cooling, bottle-shape) geometries.
Matthew Memmott +2 more
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Assessment of void fraction predictability of system codes in subchannels
Kerntechnik, 2018Abstract Dedicated subchannel analysis codes have been employed to subchannel analyses. However, the recent development of thermal-hydraulic system codes with advanced two-phase flow models and three-dimensional components has resulted in more accurate and precise prediction of multiphase phenomena in nuclear reactor systems.
Y. S. Lee, T. Kim
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Optimal Rate-Diverse Wireless Network Coding Over Parallel Subchannels
IEEE Transactions on Communications, 2020This paper derives the maximum achievable sum-rate and presents the optimal encoding/decoding framework for rate-diverse wireless network coding (RD-WNC) over broadband channels consisting of multiple parallel subchannels. RD-WNC applies to a communication scenario in which a base station wants to deliver two different messages with different rates to ...
Taotao Wang +2 more
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Development and Validation of Subchannel Code SUBSC
2017SUBSC was developed to simulate thermal–hydraulic phenomena in the core of pressurized water reactors, as well as innovative reactors operated with supercritical water as coolant. Both precise IAPWS-IF97 formulations and approximating polynomial correlations were implemented to calculate properties of water.
Jun Chen +4 more
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Improvement of the Subchannel Flow Mixing Model of the MARS Code
Nuclear Technology, 2006MARS is a best-estimate system analysis code that is based on the RELAP5/MOD3 and COBRA-TF codes. The COBRA-TF code was adapted as a three-dimensional thermal-hydraulic module in MARS. It uses a two-fluid, three-field model for two-phase flows and has a subchannel flow mixing model.
Jae Jun Jeong +2 more
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Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
Volume 7A: Thermal-Hydraulics and Safety Analysis, 2022Abstract As one of the important components in PWR cores, spacer grids can maintain the position of the rods during operation as well as promote fluid motion. The overall physical phenomena and local effects introduced by spacer grids can be accounted for the crossflow mixing model.
Si Ying Dong +3 more
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