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This research offers a fuel conversion from rod type to MTR-plate type for solving the operation problems engaged in Bandung-TRIGA 2000 Reactor. In this work, neutronic behaviour of the new core configurations are simulated, which include the calculation of criticality parameters and core management...

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Main Author: BASUKI ( NIM : 20211020), PRASETYO
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/19149
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:19149
spelling id-itb.:191492017-09-27T14:41:02Z#TITLE_ALTERNATIVE# BASUKI ( NIM : 20211020), PRASETYO Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/19149 This research offers a fuel conversion from rod type to MTR-plate type for solving the operation problems engaged in Bandung-TRIGA 2000 Reactor. In this work, neutronic behaviour of the new core configurations are simulated, which include the calculation of criticality parameters and core management. Simulative studies are carried out by using MCNPX as a tool for the calculation of all the parameters. There are two core configuration designs varied in the position of the control rods and usage of different reflector material (graphite and Beryllium). The configuration design 2 is chosen as the best core configuration, in which the control rods are positioned on the grid B2, D2, B4, D4, and Be reflector is installed surrounding the core. This configuration gives the value of core excess reactivity of $ 13.776, and the shutdown margin reactivity of $ -12.155, the number of fuel elements in the initial core configuration are 18 fuel assemblies. Considering one stuck rod criteria, the initial configuration with 18 fuel elements is still pretty safe when one control rod from any grid position fails to drop – in this configuration, control rod in position grid D2 has the biggest reactivity, still gives reactivity at $ -0.765. At the core management testing, reactor was simulated to operate during 20 periods at power 2 MWth, and the core equilibrium condition is reached with average core excess reactivity at $ 11.537, with an average replacement fuel elements of 8 assemblies per period, and the length of the period of operation of an average 444 days. Average power density for each operation period is 249.61 W/cm3 and power peaking factor radially at 1.238. Neutron flux that can be achieved in 2 MWth power varies from 5.76 x 1013 to 6.62 x 1013 neutron/cm2.sec. 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 This research offers a fuel conversion from rod type to MTR-plate type for solving the operation problems engaged in Bandung-TRIGA 2000 Reactor. In this work, neutronic behaviour of the new core configurations are simulated, which include the calculation of criticality parameters and core management. Simulative studies are carried out by using MCNPX as a tool for the calculation of all the parameters. There are two core configuration designs varied in the position of the control rods and usage of different reflector material (graphite and Beryllium). The configuration design 2 is chosen as the best core configuration, in which the control rods are positioned on the grid B2, D2, B4, D4, and Be reflector is installed surrounding the core. This configuration gives the value of core excess reactivity of $ 13.776, and the shutdown margin reactivity of $ -12.155, the number of fuel elements in the initial core configuration are 18 fuel assemblies. Considering one stuck rod criteria, the initial configuration with 18 fuel elements is still pretty safe when one control rod from any grid position fails to drop – in this configuration, control rod in position grid D2 has the biggest reactivity, still gives reactivity at $ -0.765. At the core management testing, reactor was simulated to operate during 20 periods at power 2 MWth, and the core equilibrium condition is reached with average core excess reactivity at $ 11.537, with an average replacement fuel elements of 8 assemblies per period, and the length of the period of operation of an average 444 days. Average power density for each operation period is 249.61 W/cm3 and power peaking factor radially at 1.238. Neutron flux that can be achieved in 2 MWth power varies from 5.76 x 1013 to 6.62 x 1013 neutron/cm2.sec.
format Theses
author BASUKI ( NIM : 20211020), PRASETYO
spellingShingle BASUKI ( NIM : 20211020), PRASETYO
#TITLE_ALTERNATIVE#
author_facet BASUKI ( NIM : 20211020), PRASETYO
author_sort BASUKI ( NIM : 20211020), PRASETYO
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/19149
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