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Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
Fukushima Daiichi Byu Presentation
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Fukushima Daiichi Byu Presentation

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This presentation provides an overview of the nuclear accidents that occurred at the Fukushima I power plant on March 11, 2011.

This presentation provides an overview of the nuclear accidents that occurred at the Fukushima I power plant on March 11, 2011.

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  • 1. Fukushima Dai-ichiNuclear Power Station Accident
    by
    Joseph S. Miller
    EDA, Inc
    presented at
    ASME Energy Committee Colloquium
    May 10, 2011
    Brigham Young University
  • 2. Introduction
    Over 35 Years in the Nuclear Power Industry
    MS Nuclear, BS Mechanical, BS Industrial
    Worked at a BWR Nuclear Power Station for 9 years.
    Responsible for fuel, safety analyses and PRA.
    Responsible for the Nuclear Steam Supply Systems
    Technical Support Manager for Emergency Response Organization.
    Supported the Nuclear Regulatory Commission (NRC) in reviewing Nuclear Power Plant Safety Systems.
  • 3. Acknowledgement for Use of their Reference Material
    Thanks to Japanese Industrial Atomic Forum (JIAF)
    Tokyo Electric Power Company (TEPCO)
    AREVA PowerPoint- The Fukushima Daiichi Incident – Dr. Matthias Braun
    Nuclear and Industrial Safety Agency (NISA) & Japan Nuclear Energy Safety Organization (JNES) on Plant Data
    Lake H. Barrett- Foundation For Nuclear Studies Briefing
    General Electric
    VGB Power Tech
  • 4. The Fukushima DaiichiAccident
    Plant Designs (Covered by Tom Hafera)
    What Happened?
    Accident Progression
    Spent fuel pools
    Radiological releases
    Impact on US
  • 5. PWR – Pressurized Water Reactor
  • 6.
  • 7.
  • 8.
  • 9. Nuclear Chain Reaction
  • 10.
  • 11. What Happened?
  • 12.
  • 13.
  • 14.
  • 15.
  • 16.
  • 17. The Real Catastrophe was from the Tsunami
    26,000 (dead &missing) & 130,000 homeless (April 28, 2011)
    Lead four plants at Fukushima I to fuel damage and large releases of radiation
  • 18.
  • 19. Tsunami Size Was Accident Cause 3/11 15:45 at Fukushima I
  • 20. The tsunami hits Fukushima I
  • 21.
  • 22.
  • 23.
  • 24. Plant Designs - Fukushima Dai-Ichi
    BWR is a Boiling Water Reactor
    Unit 1 is BWR/3
    Units 2-4 are BWR/4
    There are 56 Reactors in Japan (1-FBR, 4-ABWR, 29-BWR, 23-PWR) compared to 104 Reactors in the USA (35 BWRs & 69 PWRs)
    The Fukushima I reactors began operation in the 1970’s so they are all thirty - forty years old.
    Fukushima I Units 1-4 all are early vintage Mark I Containment Designs
  • 25. What happened?
    • The plant was immediately shut down (scrammed)
    when the earthquake first hit. Off-Site power was lost.
    • Emergency Diesel Generators (EDGs) started to provide backup electrical power to the plant’s backup cooling system. The backup emergency systems worked.
    • 26. All AC power to the station was lost when the tsunami flooded the EDGs, which occurred about 1 hour after the earthquake.
    • 27. At that point, the plant experienced a complete blackout (no AC electric power at all). Commonly called a “Station Blackout”.
    • 28. Only battery power was left.
  • When it Started
  • 29. Containment Isolation
  • 30. The Tsunami Hits
  • 31. Decay Heat
  • 32. Typical ECCS for BWR/3 & /4
  • 33. What happened in Unit 1?
    • Initially the Isolation condenser (IC) for Unit 1, which uses the CST water as a heat sink, was used to remove the decay heat from the shutdown reactor. After 1 or 2 hours, the 26,000 gallons of water in the IC is boiling, the CST water was not available and no heat removal other than IC boiling was available for Unit 1.
    • 34. Boiling began in the suppression pool and the drywell pressure began to increased in about 11 hours after the SBO.
    • 35. In about 16 hours the water level in the core began to decrease and core degradation occurred (through some combination of zirconium oxidation and clad failure).
    • 36. Venting occurred at about 23 hours after SBO and the hydrogen explosion occurred in the RB about 1 hour later.
    • 37. Sea water was injected into the core at about 31 hours after SBO.
  • Unit 1 Cooled with Isolation Condenser for 4-12 Hours
    • Draws steam from main steam line via natural circulation and returns to recirculation suction line.
    • 38. Tank is 55 feet long, 12 feet in diameter
    • 39. 26,000 gallon tank
    • 40. Make-up to IC tank is from CST via AC pumps
    • 41. W/O AC, water in tank is an effective coolant for about 2-6 hours
  • Unit 1 Primary Containment Pressure (D/W) & Reactor Pressure (3/11 – 3/16)
  • 42.
  • 43. What happened Unit 2?
    • Turbine Driven Reactor Core Isolation Cooling (RCIC) system for Unit 2, which operates on steam from the reactor.
    • 44. The RCIC turbine drives a pump using make-up water from the wet well or CST
    • 45. High Pressure Coolant Injection (HPCI) wasn’t used or did not work for Unit 2
    • 46. DC power from batteries and/or the use of DC powered pumps were lost after 70 hours, which is phenomenal considering that they are only designed to last 8 hours.
    • 47. Although sea water was injected within an hour after the loss of RCIC, it appears that water level continued to decrease in the RV and DW pressure increased. Significant pressure increases were observed in the RV.
    • 48. No venting of the DW was observed
    • 49. DW pressure stayed high on 3/15 00:00 and an explosion was heard in the lower part of the reactor building.
    • 50. It is believed that the primary containment was damaged.
  • Units 2&3 Cooled with reactor core isolation cooling (RCIC) for Unit 2 (66 hours) and Unit 3 (35 Hours)
  • 51. Isolation Condenser (Unit 1) and RCIC (Units 2 & 3) Were Used to Cool the Plants
  • 52. Unit 2 Primary Containment Pressure (D/W) & Reactor Pressure (3/11 – 3/17)
  • 53. What happened Unit 3?
    • Turbine Driven Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI) systems were used to cool Unit 3. Steam from the reactor turns a turbine that powers a pump to send make-up water from the wet well or CST to the reactor.
    • 54. DC power from batteries and/or use of DC powered pumps were lost after 35 hours (half the time when using only RCIC system for Unit 2), which is great considering that they are only designed to last 8 hours.
    • 55. Sea water was injected within 6 hours after the loss of RCIC & HPCI, and it appears that water level continued to decrease in the RV and DW pressure increased. Core damaged was assumed to occur during this time period.
    • 56. Venting of the DW was observed at 43 hours and at 64 hours after SBO.
    • 57. An explosion in the top of the reactor building occurred 4 hours after second venting began.
  • Unit 3 Cooled with RCIC and high pressure coolant injection (HPCI) for 35 Hours
  • 58. Unit 3 Primary Containment Pressure (D/W) & Reactor Pressure (3/11 – 3/17)
  • 59.
  • 60. Units 1, 2 & 3 Water Level
  • 61. Units 1, 2 & 3 Reactor Pressure
  • 62. Units 1, 2 & 3 Drywell Pressure
  • 63. RCIC Works for about 66 Hours (Unit 2) and 34 Hours (Unit 3)
    • RCIC Pumps Stop
    • 64. 3/14 13:25 in Unit 2
    • 65. 3/13 2:46 in Unit 3
    • 66. Decay Heat Causes the water to boil in the reactor Vessel and the pressure rises in the Reactor Vessel.
    • 67. The steam is released into the wet-wet through the SRVs
    • 68. Since there is no make up, the water level falls in the reactor vessel
  • Fuel in Top of Core is Uncovered
  • 69. Zr-Water Begins at
  • 70. Release of Fission Products
  • 71. Containment is Last Barrier
  • 72. Venting the Containment
  • 73. Hydrogen Explosion Units 1 & 3
  • 74.
  • 75.
  • 76. Damage to Torus Unit 2
  • 77.
  • 78. Radiation Levels
  • 79.
  • 80. Fukushima I Fuel Pools
  • 81. Fukushima Dai-ichi Site Reactor and Fuel Specifications
  • 82.
  • 83.
  • 84.
  • 85.
  • 86.
  • 87.
  • 88.
  • 89.
  • 90.
  • 91. Fukushima Observations
    Not a Public Heath Catastrophe
    Inconsequential to Earth/Tsunami Impacts
    The Fukushima event rating was provisionally increased from level 5 to level 7 by Japanese officials on April 12, due to computer analyses indicating total discharged iodine-131 and caesium-137 in the early days of the event were sufficient to warrant an increased rating level. This rating increase did not reflect any new event. The radioactive release from Fukushima is very roughly estimated by Japanese officials to be about 10 percent of that released from the Chernobyl accident – with very important differences.
  • 92. Fukushima Observations
    Not a Public Heath Catastrophe
    The most important difference between Chernobyl and Fukushima is no deaths or illness among the public are expected from the Fukushima incident. The Chernobyl accident emitted radioactive particles high into the atmosphere, which spread downwind across Europe, and a reactor fire continued this process for at least 10 days. Radiation from the Fukushima incident is mostly in the form of liquid runoff into the ocean and low-altitude particles that have frequently blown out into the ocean. At Fukushima, the reactor fuel remains inside the primary containment structures, whereas the Soviet Chernobyl design did not have a containment structure.
  • 93. Fukushima Observations
    What is the risk of radioactivity getting into the US food supply?
    Normally very little food from the Fukushima region is imported into the USA. Affected foods from the region around the Fukushima plant have been banned from export by the Government of Japan. Any food from that area not already restricted by the Government of Japan will be detained for testing by the U.S. Food and Drug Administration (FDA) and not allowed into the USA unless shown to be absolutely free of contamination.
  • 94. Three Mile Island History
    Reactor Scram: 04:00 3/28/79
    Core melt and relocation: ~ 05:00 –07:30 3/28/79
    Hydrogen Deflagration: 13:00 3/28/79
    Recirculation Cooling: Late 3/28/79
    Phased Water Processing: 1979‐1993
    Containment Entry: July 1980
    Reactor Head removed and core melt found: July 1984
    Start Defuel: October 1985
    Shipping Spent Fuel: 1988‐1990
    Finish Defuel: Jan 1990
    Evaporate ~2M gallons Processed Water: 1991‐93
    Cost: ~$1 Billion
  • 95. Impact on US Reactors
    US has implemented B.5.b requirements in 2008
    Beyond Severe Accident Guidelines
    Onsite high pressure portable pump
    Procedures and appropriate staging areas and requirements for fire hoses and equipment on site
    MOUs with fire local fire stations to establish the plant as a priority in case of an emergency.
  • 96. Impact on US Reactor
    Some of the things that should be reviewed
    Review all external events, i.e., fire, flooding, explosions and earthquake, to ensure that there is backup emergency equipment that can support a station black out.
    Review training for extreme station Blackout events and procedure.
    Ensure that emergency batteries are qualified for worst case events for fl0od, fire, explosions and seismic.
    The portable high pressure pump and associated equipment that was required because of B.5.b should be housed in a structure that is qualified for worst case fire, flood, explosion and seismic events.

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