PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE

Preliminary study of plutonium multiple recyling strategy on sodium cooled fast reactor has been done. This reactor has thermal power of 714 MW and utililize UO2-PuO2 as a fuel and sodium as a coolant of the reactor. In this study, two kinds of recycling schemes has been simulated. In the first recy...

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Main Author: SETIAWAN (NIM 10205076), AHMAD
Format: Final Project
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/9848
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:9848
spelling id-itb.:98482017-09-27T11:45:15ZPRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE SETIAWAN (NIM 10205076), AHMAD Indonesia Final Project INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/9848 Preliminary study of plutonium multiple recyling strategy on sodium cooled fast reactor has been done. This reactor has thermal power of 714 MW and utililize UO2-PuO2 as a fuel and sodium as a coolant of the reactor. In this study, two kinds of recycling schemes has been simulated. In the first recycling scheme, concentration of plutonium in fuels are 19% and 20% respectively with natural uranium in the beginning of recycling step. To keep the criticality of reactor, enriched uranium is required for the next step of recycling. For the second recycling, concentration of plutonium in the fuel is made unchange (19%) and uranium enrichment is varied (5%-7%) to keep the criticality of reactor. The first recyling scheme with 19% and 20% of plutonium in the fuel, the concentration of plutonium in the spent fuel tends to decreas. More uranium enrichment is needed to keep reactor on critical condition. For scheme with plutonium 20% in fresh fuel, uranium enrichment of 5.25% can maintain the criticality of reactor after several recycling cycle. The result of the second recycling shows that more step of recycling, the concentration of fissile plutonium become smaller. Total burnup periode in this study is 1440 days. Cell calculation has been done by using PIJ modul of SRAC 2002 code with JENDL-32 as nuclear data library. <br /> 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 Preliminary study of plutonium multiple recyling strategy on sodium cooled fast reactor has been done. This reactor has thermal power of 714 MW and utililize UO2-PuO2 as a fuel and sodium as a coolant of the reactor. In this study, two kinds of recycling schemes has been simulated. In the first recycling scheme, concentration of plutonium in fuels are 19% and 20% respectively with natural uranium in the beginning of recycling step. To keep the criticality of reactor, enriched uranium is required for the next step of recycling. For the second recycling, concentration of plutonium in the fuel is made unchange (19%) and uranium enrichment is varied (5%-7%) to keep the criticality of reactor. The first recyling scheme with 19% and 20% of plutonium in the fuel, the concentration of plutonium in the spent fuel tends to decreas. More uranium enrichment is needed to keep reactor on critical condition. For scheme with plutonium 20% in fresh fuel, uranium enrichment of 5.25% can maintain the criticality of reactor after several recycling cycle. The result of the second recycling shows that more step of recycling, the concentration of fissile plutonium become smaller. Total burnup periode in this study is 1440 days. Cell calculation has been done by using PIJ modul of SRAC 2002 code with JENDL-32 as nuclear data library. <br />
format Final Project
author SETIAWAN (NIM 10205076), AHMAD
spellingShingle SETIAWAN (NIM 10205076), AHMAD
PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
author_facet SETIAWAN (NIM 10205076), AHMAD
author_sort SETIAWAN (NIM 10205076), AHMAD
title PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
title_short PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
title_full PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
title_fullStr PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
title_full_unstemmed PRELIMINARY STUDY OF PLUTONIUM MULTIPLE RECYCLING STRATEGY ON SODIUM COOLED FAST REACTOR [SFR] BY USING PIJ MODULE OF SRAC 2002 CODE
title_sort preliminary study of plutonium multiple recycling strategy on sodium cooled fast reactor [sfr] by using pij module of srac 2002 code
url https://digilib.itb.ac.id/gdl/view/9848
_version_ 1822016167580008448