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The neutron kinetics of the Molten Salt Reactor is influenced by the flow rate of the fuel. This research analyzed flow rate changes by the molten salt fuel <br /> <br /> <br /> at MSR Fuji-12 with composition LiF-BeF2-ThF4-233UF4 respectively 71.78%- 16%-11.86%-0.36% Calculation...

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Main Author: KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/20192
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:20192
spelling id-itb.:201922017-09-27T14:41:03Z#TITLE_ALTERNATIVE# KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/20192 The neutron kinetics of the Molten Salt Reactor is influenced by the flow rate of the fuel. This research analyzed flow rate changes by the molten salt fuel <br /> <br /> <br /> at MSR Fuji-12 with composition LiF-BeF2-ThF4-233UF4 respectively 71.78%- 16%-11.86%-0.36% Calculation process in this study is performed numerically by SOR and finite difference methode, as well as using the C programing language. Data of reactivity, neutron flux, and the macroscopic fission cross section are used were obtained from the calculation of SRAC CITATION with JENDL-4.0 data library. <br /> <br /> <br /> The results of this calculation is known that speed setting of flow rate by MSR Fuji-12 fuel salt can be used to determine the level of criticalty of the reactor when operate at the first year until the fifth year. 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 neutron kinetics of the Molten Salt Reactor is influenced by the flow rate of the fuel. This research analyzed flow rate changes by the molten salt fuel <br /> <br /> <br /> at MSR Fuji-12 with composition LiF-BeF2-ThF4-233UF4 respectively 71.78%- 16%-11.86%-0.36% Calculation process in this study is performed numerically by SOR and finite difference methode, as well as using the C programing language. Data of reactivity, neutron flux, and the macroscopic fission cross section are used were obtained from the calculation of SRAC CITATION with JENDL-4.0 data library. <br /> <br /> <br /> The results of this calculation is known that speed setting of flow rate by MSR Fuji-12 fuel salt can be used to determine the level of criticalty of the reactor when operate at the first year until the fifth year.
format Theses
author KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA
spellingShingle KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA
#TITLE_ALTERNATIVE#
author_facet KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA
author_sort KUNCORO AJI (NIM : 20212023); Pembimbing : Dr. Abdul Waris, INDARTA
title #TITLE_ALTERNATIVE#
title_short #TITLE_ALTERNATIVE#
title_full #TITLE_ALTERNATIVE#
title_fullStr #TITLE_ALTERNATIVE#
title_full_unstemmed #TITLE_ALTERNATIVE#
title_sort #title_alternative#
url https://digilib.itb.ac.id/gdl/view/20192
_version_ 1821120075527094272

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