As the important parts of the fuel assemblies of Pressurized Water reactors (PWR), the presence of spacer grids promotes the local heat transfer adjacent to the wall downstream the grids by causing cross and swirl flo...
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ISBN:
(纸本)9781629937212
As the important parts of the fuel assemblies of Pressurized Water reactors (PWR), the presence of spacer grids promotes the local heat transfer adjacent to the wall downstream the grids by causing cross and swirl flow between and within sub-channels, which greatly widen the thermal hydraulic safety margin. Recent years, with tremendous development of computer technologies and numerical simulations, Computational Fluid Dynamics codes (CFD) are widely adapted to the designs and selections of spacer grid. This paper presents a CFD methodology to evaluate two-phase mixing characteristics on PWR fuel rod bundle with spacer grids. Numerical simulations on air and water flow were carried out with CFX 12.0 for two different patterns of spacer grids. In addition, they were selected for the critical heat flux (CHF) tests with FREON in Nuclear Power Institute of China (NPIC). Comparisons of numerical researches and experimental results show that the CFD methodology to predict bubble congregating tendency adjacent to the surface of fuel rod was validated.
As a key equipment,reactor Vessel Internals influence the safety of nuclear power *** is a rigid requirement to stock of reactor Vessel Internals because of the high temperature,high pressure and high dose *** the sta...
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As a key equipment,reactor Vessel Internals influence the safety of nuclear power *** is a rigid requirement to stock of reactor Vessel Internals because of the high temperature,high pressure and high dose *** the stainless steel usually used in different nations,the paper analyze the corrosion resistance property,weldability and irradiation property and recommend the optimum stock option.
CSR1000(China Supercritical water-cooled reactor with the rated electric power of 1000 MWe) put forward by NPIC (Nuclear Power Institute of China) proposed a new design of fuel assembly cluster with two-pass core arra...
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ISBN:
(纸本)9781629937212
CSR1000(China Supercritical water-cooled reactor with the rated electric power of 1000 MWe) put forward by NPIC (Nuclear Power Institute of China) proposed a new design of fuel assembly cluster with two-pass core arrangement. In this paper, subchannel analysis code ATHAS which has added new heat transfer and friction coefficient correlations obtained from experiment on T/H characteristics of SCW carried out by NPIC has been used to analyze the thermal-hydraulics characteristics of CSR1000. The subchannel analysis results have shown that the design basically meets the requirements of thermal-hydraulics design and remains some margins for safety analysis.
A robust adaptive backstepping control method for electro-hydraulic position servo system is investigated. For uncertainties nonlinear math model of electro-hydraulic position servo system, designed cerebellar model a...
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Electrical discharge machining (EDM) processing is generally applied on the area of molding plastic component or mating surface required high accuracy. The areas determine the quality of the plastic components. The pr...
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The advanced pressurized water reactor with a tight hexagonal lattice core design has its potential to improve uranium utilization. With a smaller pitch-to-diameter ratio (p/d) ranging from 1.05 to 1.20, a major probl...
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