slovak university of technology in bratislava
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Slovak University of Technology in Bratislava Faculty of Electrical Engineering and Information Technology Institute of Nuclear and Physical Engineering. Future perspectives of nuclear energy. Štefan Čerba. [email protected]. Contents. Introduction. Nuclear energy in global. - PowerPoint PPT PresentationTRANSCRIPT
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SLOVAK UNIVERSITY OF TECHNOLOGY IN BRATISLAVAFaculty of Electrical Engineering and Information TechnologyInstitute of Nuclear and Physical Engineering
Štefan Čerba
Future perspectives of nuclear energy
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ContentsIntroduction
Nuclear energy in global and in Slovakia
The role of nuclear energy in a future of Slovakia
Advantages of the fast neutron spectrum
GEN IV nuclear energy systems
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Introduction
Nuclear Coal Hydro Wind Solar0
10
20
30
40
50
60
70
80
90
100 90.5
60
45
2015
88.3
27.121.5
15 15
WorldSlovakia
Pow
er lo
ad [%
]
Nuclear Coal Plynové Wind Solar Hydro0
0.05
0.1
0.15
0.2
0.25
Prod
uctio
n co
st $
/ KW
h
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Nuclear energy in global
37.50%
24.30%
25.50%
6.30%
6.50%
World
OilGasCoalHydroNuclear
45.20%
24.70%
15.30%
0.04%
14.40%
Europe
OilGasCoalHydroNuclear
Oil Natural gas Coal Uranium0
50
100
150
200
250
300
4970
280 270
Year
s
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Nuclear energy in global
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Nuclear energy in Slovakia50.
67%
17.46%
19.10% 9.1
4%3.62%
Nuclear Thermal Hydro OtherImport
23.39%
33.21%
31.85%
11.54%
Nuclear ThermalHydro Other
Total production: 29.309 TWh[1]
Total consumption: 29.830 TWh
Import: 521 GWh
Installed capacity: 7780 MWe
Till 2030 -3850 MWe
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Nuclear power plants in SlovakiaPower plant EBO V2
BohuniceEMO 1,2
MochovceEMO 3,4
MochovceEBO V1
BohuniceA1
BohuniceReactor type VVER 440/
v213VVER 440/
v213VVER 440/
v213VVER 440/
v230 KS 150
Thermal power [MWth]
1471 1471 1375 (1471) 1375 560
Gross electric power [MWe]
500 500 440 (500) 440 150
Reactor units 2 2 2 2 1Launch 1984/1985 1998/2000 2012/2013 1978/1980 1972Shutdown 2024/2025 2038/2040 2052/2053 2006/2008 1979Status operating operating Built shutdown shutdown
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The future of nuclear energy
6,948,762,823 84,739
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The future of nuclear energy
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Classification of nuclear reactors
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Generation four international forum
Goals:o Sustainability,o Economy,o Safety and reliability,o Proliferation resistance and physical protection.
SFR – Sodium-cooled fast reactor
LFR – Lead-cooled fast reactor,
GFR – Gas cooled fast reactor.
VHTR – Very high temperature reactor,
SCWR – Supercritical water-cooled reactor,
MSR – Molten salt reactor,
GIF2002
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Fast neutron spectrum
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Fast neutron spectrum
• Thermal spectrum:
• Fast spectrum:
Increasing n energy -->
Enrichment < 5 %
Enrichment = 20 - 30 %
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SFR – Sodium-cooled fast reactor• Sodium coolant,• Fast neutron spectrum,• Closed fuel cycle,• Electricity production and actinide transmutation,• Operation: 550 °C - low pressure,• Oxide, carbide or metallic fuel with U, Pu and MA content,• Burnup up to 200 GWd/tHM,
• SF reprocessing via PUREX.• EBR–I, Phenix, BN-600.• ASTRID - demonstrator
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LFR – Lead-cooled fast reactor
• Liquid lead coolant, • Fast neutron spectrum,• Operation in closed fuel cycle,• Actinide transmutation, • Electricity production,• Possibility of hydrogen production,• Operation conditions: 550 °C at low pressure,• technology base: Russian α type submarines (Pb-Bi).
2 concepts:- Reference design: 600 MWe (ELSY) – (U,Pu,MA)O2 fuel- Modular design: 20 MWe (SSTAR) – (U,Pu,MA)N fuel (t=650 °C).
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GFR – gas cooled fast reactor
• He coolant,• Fast neutron spectrum,• Closed fuel cycle,• More effective natural U utilization,• Reduction of the long-lived RAV radiotoxicity,• Operation conditions: 750 °C and 7 MPa,• Efficient electricity generation,• Hydrogen production and process heat supply,• Innovative (U,Pu,MA)C –SiC fuel,• Unique DHR system,• ALLEGRO – demonstrator.
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VHTR – very high temperature reactor• Helium coolant,• Graphite moderator,• Thermal neutron spectrum,• Once-through U fuel cycle,• Cogeneration of electricity and hydrogen,• Process heat applications,• Operation at high temperatures 900 - 1000 °C and high pressure 7 MPa,• UO2 – SiC fuel,
• Very high thermal efficiency.
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SCWR – Supercritical water-cooled reactor
• Operation above the TD critical point of water(t=374 °C, p=22MPa, ρ=0.32 g/cm3),• Either thermal or fast neutron spectrum,• Possible once-though or closed fuel cycle,• Base-load electricity production,• Thermal efficiency η>50 %,• Investment and operation costs comparable with LWRs,• UO2 fuel,• target burnup - 45 GWd/tHM.
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MSR – molten salt reactor• liquid fluoride salt coolant,• UF, PuF – ZrF, NaF, LiF,• Thermal and epithermal neutron spectrum,• Excellent neutron balance,• Actinide transmutation,• Electricity generation,• Hydrogen production,• Process heat supply,• Continuous refueling,• Possible addition of actinide feeds during operation,• Th-U Breeder fuel cycle.
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ESNII - European Sustainable Nuclear Industrial Initiative
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“The country which first develops a breeder reactor will have a great competitive advantage in atomic energy.”
E. Fermi
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Backup slide 1
1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 21000
1000
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moderate high
Time
Inst
alle
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paci
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we]
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Backup slide 2
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Backup slide 3
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Backup slide 4
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Backup slide 5
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Backup slide 6
1990 2000 2010 2020 2030 2040 2050 20600
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Without GFRWith GFR
Time [years]
Pu in
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