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INDONESIANUCLEAR POWER PLANT
BLUE PRINT
Lecturer : SYARIFFUDDIN MAHMUDSYAH
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Pertimbangan Penggunaan PLTN
KOMPETITIF SECARA EKONOMIS
KEHANDALAN TINGGI
TINGKAT KESELAMATAN TINGGI
PENERIMAAN MASYARAKAT
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KOMPETITIF SECARA EKONOMIS
BIAYA INVESTASI
BIAYA BAHAN BAKAR
BIAYA O & M
DALAM JANGKA BIAYA PEMBENGKITAN
KOMPETITIF DIBANDING PEMBANGKIT
LISTRIK JENIS LAIN
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KEHANDALAN TINGGI
PLTN GENERASI BARU MEMILIKI JAM OPERASI TAHUNAN DIATAS 8OOO JAM
WAKTU MAINTENANCE PENDEK
PENGGANTIAN BAHAN BAKAR NUKLIR LEBIH CEPAT
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TINGKAT KESELAMATAN TINGGI
JAMINAN KESELAMATAN PERSONIL/PEKERJA, MASYARAKAT DAN INVESTASI
JAMINAN TERHADAP PERLINDUNGAN LINGKUNGAN
JAMINAN TERHADAP KEAMANAN DAN PENYALAHGUNAAN BAHAN NUKLIR DAN RADIOAKTIF
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PENERIMAAN MASYARAKAT
MEMILIH PLTN DENGAN TEKNOLOGI YANG MAPAN
KINERJA BAIK, ASPEK KESELAMATAN DAN EKONOMI
MEMUNGKINKAN PENGGUNAAN KOMPONEN LOKAL
PENGGUNAAN PLTN GENERASI III DAN IV
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GENERASI PLTNPARAMETER GENERASI I GENERASI II GENERASI III GENERASI IV
KARAKTERISTIK PROTOTYPE,UKURAN
BERAGAM
KOMERSIAL, DAYA
BESAR, PF >
ADVANCED DESIGN,
SEDERHANA, DAYA
BESAR,
KOMPETITIF, AMAN,
NON PROLIFERASI,
LIMBAH <, KOGEN
SISTEM
KESELAMATAN
REDUNDANSI IHERENT SAFETY,
REDUNDANSI
SISTEM PASIF,
KEDELAMATAN GANDA
CORE DENSITY <,
SISTEM PASIF, EM.
PROT. AREA <
CORE DEMAGE FREQ.
(CDF)
<1/10000/REAKTOR.
TAHUN
<1/10000/REAKTOR.
TAHUN
1/1000000/REAKTOR.T
AHUN
1/1000000/REAKTOR.
TAHUN
CONTOH MAGNOX PWR, BWR, CANDU ABWR, AP 600, AP
1000
PBMR, VHTR
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Top 10 Nuclear Countries (1999)
727,9
375
306,9
160,4110,9 97,8 91,2 70,4 70,1 67,4
0
100
200
300
400
500
600
700
800
US France Japan Germany Russia Korea RP UK Canada Sweden Ukraine
bil
lio
n k
ilow
att
-hou
rs
U.S. nuclear electricity generation is:
as large as France and Japan (#2
and #3) combined; and
larger than the other 7 nations in
the top 10 combined
Source: IAEA
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Safety of Current Nuclear Plants There has not been a loss of life in the US due to commercial
nuclear plants (TMI released a small amount of radiation)
Chernobyl accident - a terrible accident with a bad design
These plants are now closed or redesigned for operation
Russian nuclear plant operations are being assisted by IAEA
Regional deregulation of the electricity industry introduces
challenges to continue & enhance the safety of nuclear plants.
- Upgrades of power plant equipment and reliable replacement schedule
- Risk-informed decision making by the industry should be cost-effective
US nuclear plants are now self-insured via Price-Anderson Act
and we should renew Price-Anderson legislation for long-term
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Nuclear Power High Level Waste (HLW)
All nuclear fuel cycle waste (except HLW) has been safely
and reliably disposed through DoE and NRC regulations;
milling, enrichment, fabrication by-products as LLW
Since 1982, US law ‘defines’ spent nuclear fuel as a HLW,
since reprocessing has not occurred since 1976 (Japan &
Europe currently reprocess spent nuclear fuel for recycle)
Spent fuel is currently stored at ~105 nuclear power plant
sites (~ 2000 mt/yr; total ~50,000 mt) & is planned to be
stored/buried at one site in the US (Yucca Mtn)
All nuclear electricity is taxed at 1mill/kwhre for a HLW
fund (~$0.8 billion/yr; total fund ~ $20 billion)
Reassert criteria, achieve licensing & begin operation of Yucca
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Evolution of Nuclear Power Systems
1950 1960 1970 1980 1990 2000 2010 2020 2030
Gen IV
Generation IV
Enhanced
Safety
Improved
Economics
Minimized
Wastes
Proliferation
Resistance
Gen I
Generation I
Early Prototype
Reactors
•Shippingport
•Dresden,Fermi-I
•Magnox
Gen II
Generation II
Commercial Power
Reactors
•LWR: PWR/BWR
•CANDU
•VVER/RBMK
Gen III
Generation III
Advanced
LWRs
•System 80+
•EPR
•AP1000
•ABWR
http://www.energy.wisc.edu
PWR Containment
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Evolution of Nuclear Power Systems
1950 1960 1970 1980 1990 2000 2010 2020 2030
Gen IV
Generation IV
Enhanced
Safety
Improved
Economics
Minimized
Wastes
Proliferation
Resistance
Gen I
Generation I
Early Prototype
Reactors
•Shippingport
•Dresden,Fermi-I
•Magnox
Gen II
Generation II
Commercial Power
Reactors
•LWR: PWR/BWR
•CANDU
•VVER/RBMK
Gen III
Generation III
Advanced
LWRs
•System 80+
•EPR
•AP1000
•ABWR
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Nuclear Safety Enhanced
Current nuclear power plants have high levels of safety: i.e., reliable operation, low occupational radioactivity dose to workers and with minimal risk and health effects from severe accidents.
Future nuclear reactor systems will meet and exceed safety performance of current reactors.
Decay heat removal, minimize transients and allow time for operator actions are the keys to successful safety performance.
Advanced LWR’s will be simplified, thus more economic and continue to minimize emissions
Deploy advanced light-water reactor systems (GenIII)
Slide 14Doc.ppt0144
The Westinghouse AP1000
A compact station• 3415 MWt. Primary system•1117 MWe•2-loops, 2 steam generators
Slide 15Doc.ppt0144
AP1000/AP600
Reactor Coolant System
Slide 16Doc.ppt0144
AP1000 Turbine-Generator
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Advanced LWR: AP-1000
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Advanced LWR: ESBWR
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Generation IV Reactor Systems
Safety: must meet and exceed current nuclear
power plant reliability, occupational radiation
exposure and risk of accident consequences
Sustainability: minimize waste streams during
spent fuel disposal or reprocessing and recycle
Proliferation and Physical Protection of facilities
Economics: continue to reduce the total cost of
electricity ($/Mwhr-e) to remain competitive with
leading technologies (e.g., gas, coal and wind)
Develop and demo advanced reactors & fuel cycles
(GenerationIV)
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Very-High-Temperature Reactor (VHTR)
oCharacteristics
o High temperature coolant
o 900 - 1000°C outlet temp.
o 600 MWth
o Water-cracking cycle
oKey Benefit
o High thermal efficiency
o Hydrogen production by water-cracking by High-Temp Electrolysis or Thermo-chemical decomposition
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Process Heat for Hydrogen Production
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1
900 C400 C
Rejected
Heat 100 C
Rejected
Heat 100 C
S (Sulfur)
Circulation
SO2+H2O
+
O221
H2SO4
SO2+
H2OH2O
H2
I2
+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)
Circulation
2H I
I2
I2
WaterWater
Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen
H2O22
1 O22121
900 C400 C
Rejected
Heat 100 C
Rejected
Heat 100 C
S (Sulfur)
Circulation
SO2+H2O
+
O221
H2SO4
SO2+
H2OH2O
H2
I2
+ 2HI
H2SO4
SO2+H2OH2O
+
+ +
I (Iodine)
Circulation
2H I
I2
I2
WaterWater
L
Liquid Metal
Hydrogen
CxHy
Carbon
Recycle
200 C 1000 C
Thermochemical
Processes
LM Condensed Phase
Reforming (pyrolysis)
Aqueous-phase
Carbohydrate
Reforming (ACR)
H2, CO2
CATALYST
AQUEOUS CARBOHYDRATE
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Hi-Temp. Electrolysis Process
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
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GAS-COOLED REACTOR
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Nuclear Power Fuel Cycle[1000 MWe-yr – (A) Once Thru (B) U-Pu recycle] IAEA-1997
Mining/Milling
Convert/Enrichment
Fuel Fabrication
Reactor (1000MWe)
Reprocessing Plant
Milling waste stream
Conv/Enrich Waste Tails
Fuel Fabrication Waste
Spent Fuel as Waste
Reprocessing Waste (FP)
U3O8 &daughters
(A)10 mt (B) 6mt
UF6 &daughters
(A) 167mt(B) 0.5mt
(A) 205mt (B)120mt
(A) 37mt (B)11.5mt
(A) 36.8mt (B) 36.4mt (U-Pu)
(A) 35.7 mt U, 0.32mt Pu(B) 36mt U, 0.5mt Pu
(B) 1.1 mt U, 5kg Pu
UO2 & daughters
(A) 0.2mt (B) 0.16mt
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Liquid-Metal Cooled Fast Reactor (LFR)
Characteristics
• Na, Pb or Pb/Bi coolant
• 550°C to 800°C outlet temperature
• 120–400 MWe
Key Benefit
• Waste minimization and efficient use of uranium resources
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To Advance the Use of Nuclear Energy:
Ensure energy security with bipartisan initiatives and an
executive branch priority on nuclear energy
Enact long-term Price-Anderson legislation
Demonstrate predictable nuclear plant licensing processes
Reassert criteria, achieve licensing & begin operation of
Yucca Mountain Repository
Deploy current light-water reactors in the U.S. (Gen-III)
Develop/demonstrate advanced reactors & fuel cycles (GenIV)
Reestablish a vibrant educational infrastructure
=>Build public confidence and support for nuclear energy