DESIGN STUDY OF HELIUM COOLED FAST REACTOR WITH MODIFIED CANDLE BURNUP SCHEME IN RADIAL DIRECTION USING NATURAL URANIUM AS FUEL
Reactor design in this research used core model balance cylinder two dimensions R-Z with core size variations 4 m3-13 m3 with interval 1 m3. The optimization of reactor design is done by lowering fuel volume fraction for several variations. This reactors system are combined with modified CANDLE (Con...
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| Format: | Theses |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/26763 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Reactor design in this research used core model balance cylinder two dimensions R-Z with core size variations 4 m3-13 m3 with interval 1 m3. The optimization of reactor design is done by lowering fuel volume fraction for several variations. This reactors system are combined with modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy producing reactor) burnup scheme in the radial direction to create long life fast reactor with natural uranium as fuel. In this scheme, the active core is subdivided into ten regions with the same volume in the radial direction. Initially, fresh fuel (natural uranium) is put in region-1, after 10 years burnup period it is shifted to region-2, fuel in region-2 is shuffled to region-3 and so on. Finally,fuel in region-9 is shuffled to region-10 until fuel from region-10 is carried out from reactor core and then fresh uranium input toregion-1. This research have investigated effect of small reactor core size change to neutronic performances. Neutronic calculation on cell is ran by SRAC code version 2002 with data library from JENDL-4.0. Reactor core calculation is ran by FI-ITB CH1 program. Result of neutronic calculation show that core size variations effected to reactor neutronic performances. Reactor cores with volume 6 m3-13 m3provide keff > 1 and the others provide keff < 1. The fuel volume fraction of 64% gives a better criticality and stability of the reactor than the other fuel volume fractions. |
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