Transcript Folie 1

The Fukushima Daiichi Incident



Matthias Braun
PEPA4-G
AREVA NP GmbH
The Fukushima Daiichi Incident

Unit I - GE Mark I BWR (439 MW), Operating since 1970
 Unit II & III - GE Mark I BWR (760 MW), Operating since 1974
Spiegel.de
The Fukushima Daiichi Incident
Service Floor (Steel)
Building (Concrete)
RPV
Containment
Pressure
suppression pool
nucleartourist.com
The Fukushima Daiichi Incident
nucleartourist.com
The Fukushima Daiichi Incident
nucleartourist.com
The Fukushima Daiichi Incident
nucleartourist.com
The Fukushima Daiichi Incident
www.zwentendorf.com
The Fukushima Daiichi Incident
nucleartourist.com
The Fukushima Daiichi Incident
Fresh Steam
Main Feedwater
Core
RPV
Containment
Pressure suppression pool
The Fukushima Daiichi Incident
Containment
Pressure suppression pool
Containment closure
Head
en.wikipedia.org/wiki/Browns_Ferry_Nuclear_Power_Plant
The Fukushima Daiichi Incident
Progression of the accident:

11.3.2011 14:46
Earthquake

SCRAM

Containment-Isolation
►
Close of fresh steam and
main feed water valves
► Only a failure of these
Valves could lead to an
early large release
The Fukushima Daiichi Incident

11.3.2011 3:41pm
Station-Blackout
►
Loss of off-site power due
to Earthquake
► Diesel startet as planed
► Tsunami damaged either
Diesel generators or
Service water supply
(Tsunami height >7m, plant
designed for 6.5m)
► Failure of all active cooling
systems

Core Isolation Pump /
Einspeisesystem TJ
►
Steam from Reactor drives
Turbine
► Turbine pumps water form
pressure suppression pool
► Needs Battery power
The Fukushima Daiichi Incident

Reactor Isolation pump
stopped
►
Either Run-out of Batteries
► Or pressure suppression
pool boils

Pressure buildup in reactor
►

Decay heat produces
steam
Opening of pressure relief
valves
►
Steam gets blown in
pressure suppression pool
The Fukushima Daiichi Incident

Dry-out of the RPV
The Fukushima Daiichi Incident

Dry-out of the RPV
The Fukushima Daiichi Incident

Dry-out of the RPV
The Fukushima Daiichi Incident

Dry-out of the RPV
The Fukushima Daiichi Incident

Dry-out of the RPV

Heat-up of the exposed fuel
The Fukushima Daiichi Incident

At ~900°C
►
~1/3 of Core uncovered
► Fracture of the Cladding
► Release of first fission
products

At ~1200°C
►
►
►
►
►
►
~1/2 of Core uncovered
Zirconium burns Steam
Zr + H20 ->ZrO + H2
Strong core heat-up
300-600kg Hydrogen
Strong Pressure buildup in
containment
The Fukushima Daiichi Incident

Strong release of fission
products




Xenon
Cesium
Iodine
….
►
Aerosols (Smoke)
► Large fraction of fission
products get scrubbed in
pressure suppression pool,
not Xenon
► Uranium/Plutonium remain
in core

At ~1800°C
►
Melting of the cladding
► Unknown if this stadium
was reached
The Fukushima Daiichi Incident

Due to hydrogen, pressure
build-up up to 8bar in
containment

Venting of containment down
to ~4 bar

Venting via pressure
suppression pool removes
significant amount of
aerosols
►
Release of small amounts
of Aerosols (Iodine,
Cesium) and
► most of radioactive noble
gases (Xenon) and
► Hydrogen
The Fukushima Daiichi Incident

Vented gas was released
inside Reactor service floor

Hydrogen combustion
blows of Service Floor
►
Explosion Unit 1:
14.3.2011 11:01AM
► Explosion Unit 3:
14.3.2011 11:01AM

Concrete Reactor building
unaffected

Explosion of the building
spectacular, but minor
importance

Deduced Informations
►
Service Floor ~8000m3
►  100 to 200kg H2
►  20% to 40% Core
oxidation
dailycaller.com
The Fukushima Daiichi Incident

Radiation released
►
►
►
►
►
►
►
Maximum ~1mSv/h on site
after venting of unit 1
Probably similar dose at
Venting of Site 2
Expected order of
magnitude by German
crisis documents
Rapid falling values to
~0.07mSv
Indicating main release
was noble gases
INES4 classified
Most probably no land
permanently contaminated
The Fukushima Daiichi Incident

Current Information
►
RPV Flooded by See water
in all 3 Units
► Containment flooded at
least in Unit 1
► Liquid level stable

Further cooling of the
containment by venting

Clogging of fuel by sea
water?
►

Rough estimate after 100h
by flooding by pure sea
water
Core status
►
Unit1: Core damaged
► Unit2: unknown
► Unit3: Core oxidized,
possibly damaged
Informations supplyed by
Google.com
GRS.de
Yoshiaki Oka, Waseda university
.
.
.
.
ENDE der Folien
Im Anschluss Orginal-Informationen
von Yoshiaki Oka und weitere
Folien über weiter denkbaren
Unfallablauf, für welchen es bis
jetzt keine Anzeichen gibt
TEPCO’s Nuclear Power Plants
suffered from big earth quake of
March 11,2011
Yoshiaki Oka
Waseda university
Prepared for the presentation at ISSCWR5 on March 14, 2011 from the request of the
organizer based on the information until March 13 in Canada. Available Information is very
limited. Recovery action is in progress. The presentation may contain misunderstandings.
The big earth quake

Attached northern part of Japan at 2:46pm of March 11, 2011.

Magnitude is 9 in Richter scale. The biggest in history.

Some earth quakes occurred along the boundary of plates. Hundreds of km of
the boundary moved, similar to the big earth quake in Indonesia.

Big Tsunami (10m) attacked northern Japan and NPP. It was bigger than
expected.

There is no damage in the central Tokyo.

Power plants including gas and coal fired ones were automatically shut down.
NPPs were also automatically shut down.
Fukushima site 1 (1F)

6 units , Unit #1, #2 , and #3 in trouble.

Unit #1: 460MWe BWR ,Unit #3,#2: 768MWe BWR

2:46pm March 11: The earth quake happened. Plants automatically shut down.
Offsite power lost. Emergency DG started up.

3:41pm Emergency DG stopped due to loss of equipment cooling water.
(Tsunami was bigger than expected.) All AC power was lost and consequential
isolation from UHS, except for IC (isolation cooling system) in 1F1. RCIC in 1F
2 Blackout + (mostly) loss of UHS

RCIC was available to makeup water in the initial stage.

SAM (Severe Accident Management) prepared in the 90’s in place such as
containment scrubbing venting, supply of water from portable water tank using
Fire Protection pump or Fire Engine and inter-connection of power supply with
other units.

Site emergency announced. (After JCO accident, emergency law was settled. It
requires report to the central government.) Evacuation up to 20km around 1F,
10km around 2F.
Summary of Site #1, Unit 1 and 3

Loss of All AC power.

Partial core uncover (1-2m) occurred.

Hydrogen generated by Zr-water reaction

CV pressure increased and CVs were vented to maintain the integrity.

Hydrogen detonation occurred in the upper part of the reactor buildings
(unit 1 on March 12 and unit 2 on March 14). 14 workers injured.

Area evacuated in 20km.

Radiation levels are low, 1mSv/h highest at the site. (Dose limit of public:
ImSv/y)




Sea water with boric acid injected into RPV and CV.
CV integrity is maintained. Large release will be not likely.
Cores are covered by water now.
Level 4 accident of IAEA.
Fukushima site #1 Unit 2 (1F2)

Loss of all AC power.

RCIC was in operation but is now lost.

Low water level in RPV and High CV pressure continue. Mobile power
supply is tried but not working well. CV vent my be considered.

Fuel is covered by water (3am of March 14), but there is a threat to core
uncovery.

Depressurization of RPV, CV venting and Seawater injection are in
preparation.
Fukushima site # 2 (2F)
10-20km from site #1

4 units: 110MWe BWR

Sea water pumps of unit 1,2 and 4 did not work due to Tsunami. The motors
were being replaced unit by unit. Recovery of the cooling were successful for
unit 1 at 3am and for unit 2 at 7am of March 14.