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 Severe accident at Unit‐2

Fukushima Daiichi Nuclear Disaster

Hydrogen explosion  at Unit‐1 

Hydrogen explosion  at Unit‐3 

RCIC tripped  after 3 days

Depressurization  delayed by the  hydrogen explosion At Units 1 and 3

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 Severe accident at Unit‐2

Fukushima Daiichi Nuclear Disaster

Depressurization  Succeeded!

Coolant injection was delayed.

Failure in suppression pool?

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 Severe accident at Unit‐2

Fukushima Daiichi Nuclear Disaster

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 Severe accident at Unit‐2

Fukushima Daiichi Nuclear Disaster

Restoration work for power supply and water injection

Vent for RV and SC was critical. SC temp. ~ Tsat

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 Severe accident at Unit‐2

Fukushima Daiichi Nuclear Disaster

DW pressure maintained at ~ 750 kPa until after 6 hours.  

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 Severe accident at Unit‐3

 Battery relieved flooding!

Fukushima Daiichi Nuclear Disaster

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 Severe accident at Unit‐3

 Battery relieved flooding!

 Operation and control of the RCIC and HPCI could be maintained.

 It was also possible to continue monitoring reactor status using meters and gauges.

 Coolant injection continued for approximately a day and a half, after which the HPCI system  was tripped to change over to injecting coolant at low pressure (with a diesel driven fire  pump).

RPV pressure was 0.58 MPa.

Safety relief valve did not work due to battery run‐out.

 However, depressurization after this took time, the water level dropped, and the result  was the generation of hydrogen and damage to the core.

Fukushima Daiichi Nuclear Disaster

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 Severe accident at Unit‐3

Fukushima Daiichi Nuclear Disaster

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 Severe accident at Unit‐3

Fukushima Daiichi Nuclear Disaster

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 Severe accident at Unit‐3

Fukushima Daiichi Nuclear Disaster

5.6 MPa 2.9 MPa

0.95 MPa

0.79 Mpa, Below the set point of the automatic isolation of the HPCI.

Due to the possibility of reactor pressure drop causing a further slowing of HPCI turbine revolution  speed, which would increase turbine vibrations and ultimately result in reactor steam release due to  equipment damage. 

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 Severe accident at Unit‐3

Fukushima Daiichi Nuclear Disaster

0.58 MPa

0.87 MPa

The SRVs did not open, although the valve status in the  MCR displayed them as functional. It is considered that  the battery capacity was enough to display the status  indicator lamps, but not enough to operate the SRVs

4.1 MPa

7.0 MPa

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 Hydrogen explosion at Unit‐4

Fukushima Daiichi Nuclear Disaster

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 Hydrogen explosion at Unit‐4

Fukushima Daiichi Nuclear Disaster

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 Hydrogen explosion at Unit‐4

Fukushima Daiichi Nuclear Disaster

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 What if?

 Easy to say “if IC were not terminated”; “if RCIC and HPCI were not stopped manually”, … ,  etc.

 These afterthoughts are not totally correct.

 True that the reactor core seemed to have survived as long as IC or RCIC/HPCI were 

operating but this does not mean that the core could avoid core damage and melting w/o  heat sinks.

Fukushima Daiichi Nuclear Disaster

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 Magnification of damage 

 Due to simultaneous accidents at Units 1~4

Fukushima Daiichi Nuclear Disaster

In this way, one of the lessons learned from the events is that the progression of the accident at one  unit had a big impact on restoration work at the other units.

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Reviews

 Development of Fukushima Daiichi accident

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 Fukushima Daini vs. Daiichi 

Fukushima Daiichi Nuclear Disaster

12 m above sea level

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 Future responses

Fukushima Daiichi Nuclear Disaster

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Fukushima Daiichi Nuclear Disaster

 Current status

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Fukushima Daiichi Nuclear Disaster

 Current status

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Fukushima Daiichi Nuclear Disaster

 Current status

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Fukushima Daiichi Nuclear Disaster

 Current status

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Fukushima Daiichi Nuclear Disaster

 Reactor Circulation Cooling

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 Ground water

Fukushima Daiichi Nuclear Disaster

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Fukushima Daiichi Nuclear Disaster

 Reactor Circulation Cooling

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Fukushima Daiichi Nuclear Disaster

 Reactor Circulation Cooling

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Fukushima Daiichi Nuclear Disaster

 Reactor Circulation Cooling

Play with subtitle

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 Choose one topic among below

 Radioactive release from the accident 

 Short term release (within a week)

 Long term release (up to now)

 Current status 

 Cooling and purification system

 Countermeasures to protect the atmosphere and the ocean

 Application of robot technology

 Recriticality concern 

 Location of the melted fuel and muon image

 Countermeasures after Fukushima accident in Korea

Assignment #2

http://www.tepco.co.jp/

Due date: April 11, 24:00

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Assignment #2

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Contents of Lecture

 Contents of lecture

 Chapter 1 Principal Characteristics of Power Reactors

Will be replaced by the lecture note

Introduction to Nuclear Systems 

CANDU

BWR and Fukushima accident

PWR (OPR1000 and APR1400)

 Chapter 4 Transport Equations for Single‐Phase Flow (up to energy equation)

 Chapter 6 Thermodynamics of Nuclear Energy Conversion Systems:

Nonflow and Steady Flow : First‐ and Second‐Law Applications

 Chapter 7  Thermodynamics of Nuclear Energy Conversion Systems :  Nonsteady Flow First Law Analysis

 Chapter 3  Reactor Energy Distribution

 Chapter 8  Thermal Analysis of Fuel Elements

Thermodynamics Heat transport

Conduction  heat transfer Nuclear system

Referensi

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