Papers by Keyword: Fuel Assembly

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Authors: Sang Youn Jeon, Kyu Tae Kim, Young Shin Lee
Abstract: This study contains several estimation methods of the static buckling load for the spacer grid of nuclear fuel assembly in pressurized water reactor. Three different estimation methods were proposed for the calculation of the static buckling loads of spacer grid. The linear and non-linear static buckling analyses were performed to estimate the static buckling load of the spacer grids using ANSYS program. The analyses results were compared with the static buckling test results. Based on the analysis and test results, the applicability of the proposed estimation method for the static buckling load of the spacer grid was investigated.
2581
Authors: Sang Youn Jeon, Young Shin Lee
Abstract: This study contains an estimation of the dynamic buckling load for the spacer grid of fuel assembly in pressurized water reactor. Three different estimation methods were proposed for the calculation of the dynamic buckling loads of spacer grid. The dynamic impact tests and analyses were performed to evaluate the impact characteristics of the spacer grids and to predict the dynamic buckling load of the full size spacer grid. The estimation results were compared with the test results for the verification of the estimation methods.
1603
Authors: Deepak Sharma, Krishna Murari Pandey
Abstract: This paper is focused on flow simulation in the sub channel of fuel rod assembly using code ANSYS Fluent 14, which is commercial computational fluid dynamics (CFD) code. Computational simulations are reported on convective heat transfer to carbon dioxide at a pressure of 7.59MPa. Pressure which is used in this simulation are just above the thermodynamic critical pressure value of CO2. These have been carried out using a variable property, elliptic computational formulation incorporating low Reynolds number turbulence models of kε. Firstly, the simulations were compared with the effect of increasing heat flux on heat transfer coefficient. It has been found that the effect of buoyancy on turbulence production and heat transfer in fluids at supercritical pressure can be very significant even under conditions of relatively low buoyancy parameter based on bulk properties. It is clear that new heat transfer correlations are needed to account for such effects on heat transfer to supercritical pressure fluids as they come to be used more and more in new energy systems applications such as, advanced water-cooled nuclear reactors, high pressure water oxidation plant for waste processing.
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Authors: Michail Gusev, Vladimir Danilov
Abstract: Creep inverse task solution for parameters identification of Zr1Nb alloy creep law is considered. Zr1Nb alloy is commonly used as a structural material for power reactor core elements. Strength and reliability justification of the fuel assembly (FA) components, manufactured from Zr1Nb alloy, requires the knowledge of the relationship between the intensity of creep strain rate, temperature and stress intensity. However, FA elements analyses performed using the known coefficients for the Zr1Nb alloy creep law, are not consistent with the experimental data. In this paper the results of parameters identification Zr1Nb alloy creep law are shown. The results are obtained using the numerical and experimental investigations of contact interaction between fuel rod and spacer grid cell. Numerical experiments, performed using verified creep law, are close to the experimental data. The results of this research can be used for a wide spectrum of thermal strength calculations of FA elements manufactured from Zr1Nb alloy.
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