DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT

Design study of Lead-cooled fast reactor for small and medium core size to optimize fuel utilization, and to optimize inherent safety of the reactor has been done. The reactors utilize UN-PuN as fuel and lead-bismuth as coolant. These reactors operate at power 600 MWth with cylindrical geometry and...

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主要作者: FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI
格式: Final Project
語言:Indonesia
在線閱讀:https://digilib.itb.ac.id/gdl/view/15600
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機構: Institut Teknologi Bandung
語言: Indonesia
id id-itb.:15600
spelling id-itb.:156002017-09-27T11:43:10ZDESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI Indonesia Final Project INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/15600 Design study of Lead-cooled fast reactor for small and medium core size to optimize fuel utilization, and to optimize inherent safety of the reactor has been done. The reactors utilize UN-PuN as fuel and lead-bismuth as coolant. These reactors operate at power 600 MWth with cylindrical geometry and 10 years reactor operation without refueling. The optimization evaluate by using SRAC code with two-dimensional core model (R-Z) <br /> <br /> <br /> Reactor design optimization is evaluated to utilize natural uranium. Optimization evaluated by divide the core into 10 axial region. After 10 years reactor operation, the first region will be shifted by the second region and continously until the tenth region. The first region will be fulfill by the fresh fuel. Fuel region consist 6,25% thorium nitride fuel and 93,75% uranium nitride. This reactor is constructed with 350 cm height and 240 cm cillinder diameter with power level 600 MWth, this reactor has the volume fraction is 65% of fuel, 10% of cladding and 25% of coolant. 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 Design study of Lead-cooled fast reactor for small and medium core size to optimize fuel utilization, and to optimize inherent safety of the reactor has been done. The reactors utilize UN-PuN as fuel and lead-bismuth as coolant. These reactors operate at power 600 MWth with cylindrical geometry and 10 years reactor operation without refueling. The optimization evaluate by using SRAC code with two-dimensional core model (R-Z) <br /> <br /> <br /> Reactor design optimization is evaluated to utilize natural uranium. Optimization evaluated by divide the core into 10 axial region. After 10 years reactor operation, the first region will be shifted by the second region and continously until the tenth region. The first region will be fulfill by the fresh fuel. Fuel region consist 6,25% thorium nitride fuel and 93,75% uranium nitride. This reactor is constructed with 350 cm height and 240 cm cillinder diameter with power level 600 MWth, this reactor has the volume fraction is 65% of fuel, 10% of cladding and 25% of coolant.
format Final Project
author FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI
spellingShingle FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI
DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
author_facet FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI
author_sort FAKHRUDDIN (NIM : 10205071 ); Pembimbing : Prof. Dr.Eng. Zaki Su’ud, FAHMI
title DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
title_short DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
title_full DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
title_fullStr DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
title_full_unstemmed DESIGN STUDY OF Pb-Bi COOLED FAST REACTOR WITH NATURAL THORIUM AND URANIUM AS FUEL CYCLE INPUT
title_sort design study of pb-bi cooled fast reactor with natural thorium and uranium as fuel cycle input
url https://digilib.itb.ac.id/gdl/view/15600
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