topik riset nuklir itb
DESCRIPTION
Presentasi mengenai topik riset yang dikerjakan di Lab.Fisika reaktor nuklir ITB.TRANSCRIPT
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Reactor Physics LaboratoryITB
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SISTEMATIKA RISET NUKLIR DI ITB1. SPINNORs2. MODIFIED CANDLE, including GCFR3. Code Development4. Nuclear Data5. Fuel Cycle and Waste Management6. Nuclear Physics Fundamental research
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Long Life Pb-Bi Cooled Fast Reactors
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SMALL SIZE Pb-Bi COOLED NUCLEAR POWER REACTORSPower Range 25MWe ~ 100MWeLong life operation without refuelingIdeal for remote area (islands): especially outside Java-Bali AreaCurrent status : Final Optimization
especially in safety, thermal system, etc.Inherent safetyNon proliferationFissile self sustain
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Very Small Size Pb-Bi COOLED NUCLEAR POWER REACTORS Power Range 5MWe ~ 25MWeLong life operation without refuelingIdeal for remote area (islands): especially outside Java-Bali Area, special purposeCurrent status : Final Optimization
especially in safetyInherent safetyNon proliferationFissile self sustain
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Medium & Large Size Pb-Bi COOLED
NUCLEAR POWER REACTORS Power Range 100MWe ~ 2000MWeFew years operation without refuelingIdeal for Java-Bali Area, special
purpose:Hydrogen ProductionCurrent status : Optimization in Neutronic design
, safety and thermal systemInherent safetyNon proliferationBreedingEconomicalLoad followerCogeneration
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ADS (Accelerator Driven System)Power range : 100KWe~50MWeFast and thermalHigh safety performanceOptimization of neutron source design and
configurationOptimization of thermal systemSafety analysis
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Pb-Bi Corrosion InvestigationClasical and Quantum Mechanical Based
simulationBased on Ab initio ModelComparation with existing experimental dataSearching for better fit structural material
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Hydrogen Production reactorsFast: Pb-Bi Cooled, Thermal : HTGR Based Selection of Best chemical mechanismThermal configuration optimization Material feasibilitySimulation system
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MODIFIED CANDLE REACTORRegion 1
Region 10
Region 9
Region 8
Region 7
Region 6
Region 5
Region 4
Region 3
Region 2
Region 1
Region 10
Region 9
Region 8
Region 7
Region 6
Region 5
Region 4
Region 3
Region 2
OUT
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Modified Candle ReactorsIn this study conceptual design study of Pb-Bi
cooled fast reactors which fuel cycle need only natural uranium input has been performed. In this case CANDLE burn-up strategy is slightly modified by introducing discreet regions.
In this design the reactor cores are subdivided into several parts with the same volume in the axial directions.
The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel.
This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle .
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Long Life Reactor With Natural Uranium as Fuel Cycle input
D:X
3C:X
2B
:X1A:0
C:X
3B:X
2A
:X1Ura
niu
m
ala
m
BOC EOC
input
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Long Life Reactor With Natural Uranium as Fuel Cycle input
time (y unit)10987654321
Ke
ff
1.05
1.045
1.04
1.035
1.03
1.025
1.02
1.015
1.01
1.005
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Thorium(Th) and Protactinium (231Pa) Based Fuel for Tight Lattice Long Life BWR
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Keff Vs Time
1.001
1.0015
1.002
1.0025
1.003
0 3 6 9 12 15 18 21 24Time (Month)
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Active Core Volume(minus reflector)17635.8 Liter
Thermal Power 620 Mwatt
Average Power Density 35.2 Watt/cc
Enrichment Uranium-233 8.1% and 11%
Percentage Protactinium-231 6.7%dan12.5%
Reactor operation time 30 year
Excess-reactivity 0.384%
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SHIP BASED NUCLEAR POWER REACTORPb-Bi Based and Water cooled basedSmall and very small sizedIdeal for remote area, emergency and
temporary developmentStatus: Final optimization and safety analysis
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Group Contant ProcessingFast group constant : general geometryThermal system: implementation & toward
general geometryInterface to other codeParalel computation
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Neutronic DesignThree dimensional system analysisAdditional featureBetter user interfaceTransport analysisSpecial investigation
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Safety AnalysisThree dimensional modelLocal blockage analysisOther Hypothetical accident analysisADS safety analysisParalel Computation
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Monte Carlo SimulationFor shielding and neutronic calculationDevelopment of generic subroutineParalel Computation
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Paralel ComputationBased on ehternet and dedicated systemBased on Socket programming or specially
developped systemDevelopment of new algorithm better fit to
paralel computation
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Intelligent computationBased on AI or JSTTo help better convergence in special
system : thermal hydraulic, and other optimization
Safety system prediction
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TOPIK BESAR: INTEGRATED SYSTEM ANALYSIS CODETAHAP I : 1.CELL HOMOGENIZATION CODE2.MULTI GROUP DIFFUSION CALCULATION3.BURNUP ANALYSIS
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MAIN PROJECT 2009: INTEGRATED NEUTRONIC CODETAHAP I :Cell Calculation CodeMultigroup Diffusion CodeBurnup Analysis code
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Analisa BurnupStandar untuk fast reactorSetara COREBURN untuk termal reactorMetoda Semi analitikClose fuel cycle
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STATUS SAAT INIIndividual code telah adaFokus IntegrasiPerluasan cakupan libraryGeneralisasi geometriAdvanced simulation method mengejar
akurasi tinggi secara ekonomis: Misal FP treatment untuk LLFP
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Cross section calculationPhenomenological and microscopic basedPhenomenological: optical modelMicroscopic model: Generating coordinat
method and Hartree Fock MethodFP Yield Calculation DWBA CodeIntermediate Energy