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 r...
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Format: | Final Project |
Language: | Indonesia |
Online Access: | https://digilib.itb.ac.id/gdl/view/73041 |
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Institution: | Institut Teknologi Bandung |
Language: | Indonesia |
Summary: | 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. |
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