III. Eurasian conference nuclear science and its application : proceedings, 5-8 October, 2004. Tashkent, Uzbekistan.

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Browsing III. Eurasian conference nuclear science and its application : proceedings, 5-8 October, 2004. Tashkent, Uzbekistan. by All Authors "10790"

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    Calculation of the temperature distribution in a triga type fuel element following the pulse operation
    (Institute of Nuclear Physics of Uzbekistan Academy of Science, Turkish Atomic Energy Authority, 2006) Büke, T.; 10790; Bölüm Yok
    Time dependence of temperature distribution in a TRIGA type fuel element following the pulse operation was calculated by using the computer code TEMPUL for different coolant velocities in the coolant channel. The effect of the air gap produced between the fuel bulk and the cladding interface by pulsing was considered in the temperature distribution calculations. The code was developed for the analysis of boiling crisis and DNB conditions in TRIGA core after the pulse operation and provided necessary database consisting of material properties for several types of TRIGA fuel. It solves the diffusion equation for heat transfer in cylindrical geometry using finite difference method. The form of flow channel is equilateral triangle, bound by three cylindrical fuel elements. The coolant in coolant channel has a constant velocity, which is an input data and that axial power distribution is a cosine function. The results from the calculation show that the fuel temperature will never be exceeded under any conditions of after the pulse operation.
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    Radiological effects of Yatağan coal-fired power plant
    (Institute of Nuclear Physics of Uzbekistan Academy of Science, Turkish Atomic Energy Authority, 2006) Barlas, F.; Büke, T.; 10790; Bölüm Yok
    Radiation dose calculations and limit radiation dose calculations have been carried out by the code CAP88-PC around the Yatağan coal-fired power plant environment by using the result of previous studies about maximum measured gross alpha activity in the flying ash samples as radioactive sources. A modified Gaussian plume equation is used to estimate the average dispersion of radionuclides released from up to six emitting sources. The sources may be either elevated stacks or uniform area sources. Assessments are done for a circular grid of distances and directions for a radius up to 80 kilometers, 16 wind sectors and 20 mesh distances around the facility in calculations. The limit doses obtained from the calculations and their radiological effects have been interpreted. Finally the effects of various radionuclides have been carried out and their results have been compared with each other.
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