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...

Full description

Saved in:
Bibliographic Details
Main Author: POEDJO RAHARDJO, HENKY
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/898
Tags: Add Tag
No Tags, Be the first to tag this record!
Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:898
spelling id-itb.:8982004-11-23T10:54:09ZPENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR POEDJO RAHARDJO, HENKY Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/898 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. text
institution Institut Teknologi Bandung
building Institut Teknologi Bandung Library
continent Asia
country Indonesia
Indonesia
content_provider Institut Teknologi Bandung
collection Digital ITB
language Indonesia
description 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.
format Theses
author POEDJO RAHARDJO, HENKY
spellingShingle POEDJO RAHARDJO, HENKY
PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
author_facet POEDJO RAHARDJO, HENKY
author_sort POEDJO RAHARDJO, HENKY
title PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
title_short PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
title_full PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
title_fullStr PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
title_full_unstemmed PENELITIAN EKSPERIMENTAL PENGARUH PEMANASAN PADA LAJU ALIRAN SATU MODEL REAKTOR NUKLIR
title_sort penelitian eksperimental pengaruh pemanasan pada laju aliran satu model reaktor nuklir
url https://digilib.itb.ac.id/gdl/view/898
_version_ 1820662804378550272