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Kecelakaan Reaktor Nuklir
Dr. Eng. Pribadi Mumpuni Adhi
Politeknik Negeri Jakarta
20181
List of MAJOR ACCIDENT IN ENERGY SYSTEM
Place year number killed comments
Machhu II, India 1979 2500 hydro-electric dam failure
Hirakud, India 1980 1000 hydro-electric dam failure
Ortuella, Spain 1980 70 gas explosion
Donbass, Ukraine 1980 68 coal mine methane explosion
Israel 1982 89 gas explosion
Guavio, Colombia 1983 160 hydro-electric dam failure
Nile R, Egypt 1983 317 LPG explosion
Cubatao, Brazil 1984 508 oil fire
Mexico City 1984 498 LPG explosion
Tbilisi, Russia 1984 100 gas explosion
northern Taiwan 1984 314 3 coal mine accidents
Chernobyl, Ukraine 1986 31+ nuclear reactor accident
Piper Alpha, North Sea 1988 167 explosion of offshore oil platform
Asha-ufa, Siberia 1989 600 LPG pipeline leak and fire
Dobrnja, Yugoslavia 1990 178 coal mine
Hongton, Shanxi, China 1991 147 coal mine
Belci, Romania 1991 116 hydro-electric dam failure
Kozlu, Turkey 1992 272 coal mine methane explosion
Cuenca, Equador 1993 200 coal mine
Durunkha, Egypt 1994 580 fuel depot hit by lightning
Seoul, S.Korea 1994 500 oil fire
Minanao, Philippines 1994 90 coal mine
Dhanbad, India 1995 70 coal mine
Taegu, S.Korea 1995 100 oil & gas explosion
List of MAJOR ACCIDENT IN ENERGY SYSTEM
List of MAJOR ACCIDENT IN ENERGY SYSTEM
Spitsbergen, Russia 1996 141 coal mine
Henan, China 1996 84 coal mine methane explosion
Datong, China 1996 114 coal mine methane explosion
Henan, China 1997 89 coal mine methane explosion
Fushun, China 1997 68 coal mine methane explosion
Kuzbass, Russia/Siberia 1997 67 coal mine methane explosion
Huainan, China 1997 89 coal mine methane explosion
Huainan, China 1997 45 coal mine methane explosion
Guizhou, China 1997 43 coal mine methane explosion
Donbass, Ukraine 1998 63 coal mine methane explosion
Liaoning, China 1998 71 coal mine methane explosion
Warri, Nigeria 1998 500+ oil pipeline leak and fire
Donbass, Ukraine 1999 50+ coal mine methane explosion
List of MAJOR ACCIDENT IN ENERGY SYSTEM
Donbass, Ukraine 2000 80 coal mine methane explosion
Shanxi, China 2000 40 coal mine methane explosion
Muchonggou, Guizhou, China 2000 162 coal mine methane explosion
Jixi, China 2002 115 coal mine methane explosion
Gaoqiao, SW China 2003 234 gas well blowout with H2S
Kuzbass, Russia 2004 47 coal mine methane explosion
Donbass, Ukraine 2004 36 coal mine methane explosion
Henan, China 2004 148 coal mine methane explosion
Chenjiashan, Shaanxi, China 2004 166 coal mine methane explosion
Sunjiawan, Liaoning, China 2005 215 coal mine methane explosion
Fukang, Xinjiang, China 2005 83 coal mine methane explosion
Xingning, Guangdong, China 2005 102 coal mine flooding
Dongfeng, Heilongjiang, China 2005 164 coal mine methane explosion
Flashback BWR
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Prinsip Kerja BWR
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http://www.nrc.gov/
BWR Mark I type Primary ContaimentVessel (PCV) – Fukushima Daichi
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Spent fuel pool Reactor Building
PCV
RPV
Drywell (D/W)
Suppression chamber
Wetwell (W/W)
Structure BWR RPV
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Multiple Barrier to confine radioactivity
ECCS : Emergency Core Cooling System
PCV : Primary Containment Vessel10PWR
Peristiwa 3/11 (Fukushima)
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Intensitas Gempa
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Penjelasan Intensitas Gempa
Magnitude-ShindoNumber (Shindo
Number in Japanese)
/ Meter reading
Effects on people
Indoor situations
Outdoor situations
ResidencesOther
buildingsLifelines
Ground and slopes
Peak ground
acceleration[
Approximate
Equivalent Rating
on Mercalli Scale
7 (7) / 6.5 and up
Thrown by the shaking and impossible to move at will.
Most furniture moves to a large extent and some jumps up.
In most buildings, wall tiles and windowpanes are damaged and fall. In some cases, reinforced concrete-block walls collapse.
Most or all residences collapse or receive severe damage, no matter how earthquake-resistant they are.
Most or all buildings (even earthquake-resistant ones) suffer severe damage.
Electrical, gas and water service are interrupted.
The ground is considerably distorted by large cracks and fissures, and slope failures and landslides take place, which can change topographic features.
Greater than 4 m/s²
X-XII
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Distribusi Ketinggian Tsunami
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Persebaran Reaktor Nuklir di Jepang
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Fukushima Daichi Site
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Fukushima Daichi Reaktor
Unit Tipe Power (Mwe) Mulai Beroperasi
F-1 BWR/3 460 3/26/1971
F-2 BWR/4 784 18/7/1974
F-3 BWR/4 784 27/3/1976
F-4 BWR/4 784 12/10/1978
F-5 BWR/4 784 18/4/1978
F-6 BWR/5 1100 24/10/1979
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Fun Fact:Unit 1 dijadwalkan berhenti beroperasi pada awal tahun 2011, tetapi pada Februari2011 regulator di Jepang mengizinkan perpanjangan untuk 10 tahun ke depan
Invasion Area Tsunami
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Situasi saat Tsunami pada F5/F6
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Situasi Tsunami pada Fukushima Daichi
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Situasi Setelah Tsunami
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Hydrogen Explosion
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Accident Outline
23RHR : residual heat removal
Safety System
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Mechanism of Isolation Condenser for BWR/2 and 3
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Terjadi pada F1
PLR : primary loop recirculation
Reactor Core Isolation Cooling System (RCIC)
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Recirculation pump
Containment Suppression Chamber
RCIC
Pump
Condensate Storage
Tank
Containment/Drywell
Recirculation Loop
(Typical of 2)
Safety/Relief valveAutomatic Depressurization System (ADS)
Terjadi pada F2 – F4
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Low Pressure Emergency Core Cooling System
Mekanisme Cooling Systen
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Injection of Seawater into RPV
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Watering Fuel Pool by Helicopter
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• Awalnya diduga penyebab ledakan dari F-3 berasal dari terbentuknya gas H2 di fuel pool, sehingga penyiraman denganhelicopter perlu dilakukan
• Karena radioaktivitas sangat tinggi dan adanya puing-puing, maka mobilpemadam tidak dapat mendekat
Seawater Injection into F-3/4 by Fire Engine
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Ledakan gas H2 pada F-4 yang sedang dalam kondisi maintenance diduga berasal dari terbentuknya gas H2 pada fuel pool yang tidaktertutup air
Core Damage and H2
Generation
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Melting Point of Structural Materials
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Distribusi Temperatur pada Fuel Pin
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Metal – Water Reaction
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Propagation of Severe Accidents in RPV
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Physical Phenomena in PCV after core damage
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(1) Fuel Coolant interaction(2) Molten Core Concrete Interaction(3) Direct Containment Heating
N2 Injection into PCV
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N2 diinjeksi ke PCV untukmengurangi kemungkinanledakan pada PCV
Leakage of Cooling Water from the Lower Part of PCV
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Polluted Water Outflow to Sea from Trench
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Mekanisme Core Damage
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Status NPP yang Lain
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Onagawa-1,2,3
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Tokai-2 (1100 Mwe)
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Fukushima Daini 1.2.3.4 units
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Three Miles Island Incident
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Overview
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•In 1979 at Three Mile Island nuclear power plant in USA a cooling malfunction caused
part of the core to melt in the #2 reactor. The TMI-2 reactor was destroyed.
•Some radioactive gas was released a couple of days after the accident, but not enough
to cause any dose above background levels to local residents.
•There were no injuries or adverse health effects from the Three Mile Island accident.
How it happened?
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• Failure of secondary loop , feedwater pump prevented send water to SG• Pressure increased, relief valve opened.• Relief valve failed to close → pressure decreased• The staff reduced emergency cooling water into primary system• Reactor core overheat → Loss of Coolant Accident
Masalah pada pompa
Relief valve stuck
Reducing flow
Core melt down
Gen III+, ESBWR
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What is ESBWR ?
• The Economic Simplified Boiling Water Reactor (ESBWR) is a 1520 MWe Generation III+ boiling water reactor.
• Certified by the US Nuclear Regulatory Commission (NRC) in 2014, the ESBWR is the world’s safest reactor.
• It has the lowest core damage frequency (industry standard measure of safety) of any Generation III or III+ reactor and can safely cool itself with no AC electrical power or human action for more than seven days.
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•Residual heat transferred to the atmosphere•11 systems eliminated from previous designs•25 percent of pumps, valves and motors eliminated
Feature and Benefits
Sirkulasi Alamiah pada ESBWR
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Overview ESBWR Feature
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ESBWR Passive Safety System
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Overview Passive Safety ESBWR
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Tugas
Menurut pendapat kalian apa yang menyebabkan kecelakaan pada reaktor nuklir Fukushima Daichi
a. Gempa/tsunami
b. H2 explosion
c. Human error saat beroperasi
d. Loss of Coolant
e. Decay heat
f. Gagalnya reaktor nuklir shutdown
g. Sudah takdir
h. Semua benar
Jelaskan jawaban kalian dan tulis pada selembar kertas max 1 halaman
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