History of nuclear power
1938– Scientists study Uranium nucleus
1941 – Manhattan Project begins
1942 – Controlled nuclear chain reaction
1945 – U.S. uses two atomic bombs on Japan
1949 – Soviets develop atomic bomb
1952 – U.S. tests hydrogen bomb
1955 – First U.S. nuclear submarine
Neutron induced fission
Inti berat dapat pecah jika ditumbuk • Tumbukan menyebabkan nucleon
kehilangan keadaan setimbangannya• Tumbukan yang keras merupakan
kondisi terbaik untuk menginduksi fisi• Neutrons merupakan proyektil ideal
untuk menginduksi fisi
Perbandingan Energi Nuklir dengan Energi Kimia
• C + O2 ➔ CO2 + 4 ev
• U-235 + n ➔ FP1 + FP2 + (2 atau 3) n + 200 Mev
• 1 eV = 1,6 x 10-19J
• 1 gram U-235 = 1/235x6,02x1023x200Mev
= 8,197x1010 Joule
= 8,197x1010/24/3600=0,949x106 watt day
~ 1 MWday
Note : Untuk 100% U-2357
Mini Quiz (1)
Jika diasumsikan energi yang dihasilkan oleh batu baraberasal dari pembakaran karbon. Maka untukmenghasilkan energi sebesar 1 MWd dibutuhkanberapa ton batu bara?
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Answer
C + O2 ➔ CO2 + 4 ev
1 gram C = 1/12 x 6,02x1023 x 4ev = 3.81 x 104J
1 MWd = 1 x 106 x (24x3600) = 8.64 x 1010 J
Sehingga untuk menghasilkan energi setara 1g U-235 dibutuhkan batu bara sebanyak 2,27 x 106 g atau 2,27 ton
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Evolusi Reaktor Daya (Generasi Reaktor)
• Gen I• Prototypes in 50’s & 60’s
• Gen II• 70’s & 80’s• Today’s Operational Reactors• BWR, PWR, CANDU, …
• Gen III• ABWR, APWR• Approved 90’s• Some Built around the World
• Gen III+• Current Advanced Designs in
the Approval Process• Pebble Bed Reactor
• Gen IV• Deploy in 2030• Economical• Safe• Minimize Waste• Reduce Proliferation
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Klasifikasi Reaktor Nuklir Fisi
• Berdasarkan perbedaan spektrum energi neutron
• Fast reactor
• Thermal reactor
• Berdasarkan jenis material yang digunakan sebagai moderator dan pendingin
• Gas (Magnox, AGR, HTGR)
• Air (LWR → BWR dan PWR, SCWR)
• Air berat (CANDU)
• Logam cair (SFR, LFR)
• Garam cair (MSR)
• Bardasarkan fungsi
• Reaktor riset (di BATAN)
• Transmutasi (ADS),
• Reaktor daya (LWR dll)12
Klasifikasi Reaktor Daya
Reactor types Reactor names Moderator Coolant
Thermal
reactors
Magnox GCR Graphite CO2
AGR Graphite CO2
PWR H2O H2O
BWR H2O H2O
BLWR(FUGEN) D2O H2O
PHWR(CANDU) D2O D2O
HTR Graphite He
THTR Graphite He
RBMK Graphite H2O
Fast reactor LMFBRs None Na or
Pb/Pb-Bi 13
Komponen Utama Reaktor Nuklir
1. Fuel (Bahan Bakar)
2. Moderator
3. Control Rods (Batang kendali)
4. Coolant (Pendingin)
5. Steam Generator
6. Turbine/Generator
7. Pumps
8. Heat Exchanger
9. CondenserReactor cooling tower
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Bahan Bakar
Enriched Fuel pellet
Properties of Uranium Oxide (UO2)
Melting point 2865 0C (5189 0F)
Density (x-ray measur.) 10.97 g/cc
Thermal conductivity 4.777 x 10-3 W/m.K at 20 0C
1.91 x 10-3 W/m.K at 1000 0C
Thermal expansion coef. (per 0C)
~1x10-5/ 0C (0 – 1000 0C)
Tensile strength 6.9 x 107 Pa (10,000 psi)
Modulus elasticity 1.72 x 1011 Pa (25x106 psi)
Cell type Face-centered cubic
Uranium-235 enrichment: 3 – 5%Max enrichment (allowed): 20%
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Mini Quiz (2)
Mengapa ada gap antara clad material dan fuelmaterial?
1. Agar mudah dalam proses fabrikasi(memasukan fuel pellet ke cladding)
2. Untuk mencegah cladding rusakapabila terjadi fuel swelling
Answer
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Schematic Diagram PLTN1. PWR
http://www.nrc.gov/Water supply pump
Circulation pump
To sea
Sea water
Steam
Water
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Mini Quiz (3)
1. Apa yang dimaksud dengan saturation temperature(temperature jenuh) air dan berapa Tsat air padatekanan 0.1 Mpa?
2. Mengapa tidak terjadi aliran dua fasa (two phaseflow) pada primary loop PWR sedangkan padasecondary loop terjadi?
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PWR Coolant Circuits
• Siklus tidak langsung : Primer dan Sekunder coolant loop
• Aliran fluida satu fasa pada reactor coolantTin = 287,7oC; Tout = 324oC; P=15.2 Mpa; Tsat = 343.2oC
• Aliran fluida dua fasa pada power conversion cycle loopTS,G = 227oC; TSG,out = 285oC; P=6.9 Mpa,Tsat=285oCTcondenser=37,8oC; 6,6kPa
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PWR PressurizerPressurizer (Saturated Liquid-Steam system: P=15,5 MPa; T=344,7oC)Control pressure in the primary system
- Pressure can be raised by heating water (electrically)
- Pressure can be lowered by condensing steam (on sprayed droplets)
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Steam Generator
Primary side,, Hot (Tin = 324˚C,, Tout = 288˚C)): High Pressure Liquid
Secondary side, Cold (Tsat = 285˚C): Lower Pressure Steam and Liquid
• Water boils on Shell Side of Heat Exchanger
• Steam Passes through Liquid Separators, Steam
Dryers
• Liquid Water Naturally Recirculates via Downcomer
• Level controlled via steam and feedwater flowrates
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Reactor Coolant Pump
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to provide forced primary coolant flow to remove the amount of heat being generated by the fission process
http://www.nrc.gov/
Schematic Diagram PLTN2. BWR
Water supply pump
Circulation pump
To sea
Sea water
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References
• Abdul Waris, Kuliah Topik Khusus Fisika Reaktor, ITB
• Jacopo Buongiorno, MIT OCW
• J.J. Duderstadt, 1976, Nuclear Reactor Analysis, John Wiley and Son
• Minoru Takahashi, Nuclear Energy System Course, Tokyo Tech
• USNRC Technical Training Center, Pressurized Water Reactor (PWR)
• USNRC Technical Training Center, Boiling Water Reactor (PWR)
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