PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR

The process of heat transfer in a nuclear reactor depends lagerly on the movement of the liquid coolant. The movement of liquid coolant (pure water) in a natural convection process is the outcome of heating. Due to latter process different temperatures axist at each point in the liquid, creating. di...

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Bibliographic Details
Main Author: POEDJO RAHARDJO, HENKY
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/898
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Institution: Institut Teknologi Bandung
Language: Indonesia
Description
Summary:The process of heat transfer in a nuclear reactor depends lagerly on the movement of the liquid coolant. The movement of liquid coolant (pure water) in a natural convection process is the outcome of heating. Due to latter process different temperatures axist at each point in the liquid, creating. different fluid mass densities. Consequently a slow motion of the cooling fluid occurs. In this research work, experiments has been carried out to determine the influence of heating on the rate of motion as an integral part of natural convection occuring in a nuclear reactor fuel element. A model of heat transfer system in a reactor is constructed, utilizing electrical heating to simulate the heating of a nuclear fuel element. To monitor the rate of mo tion, measurements on the speed of flow of the fluid has been carried out utilizing a detector in the form. of dye fluid (ink) having a specific weight equal to that of the liquid coolant. By photography the position of the dye particles in the moving liquid at timed intervals, the pattern of the velocity of the flowing fluid is recorded. From the velocity profiles in the heating area to the fringe of the boundary layer obtained at the timed intervals, the rate of flow of the cooling fluid due to heating can be determined. The result of the experiments indicate that the rate of flow is an exponential power function in regard to the heat energy applied. The model that has been designed for this purpose, may be used to study heat transfer problems in a nuclear reactor and provides a preliminary information for further investigation.