Japan Earthquake: Nuclear Plants at Fukushima Daiichi

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The Fukushima Daiichi nuclear plant is facing significant challenges following the earthquake, with reports indicating that reactor pressure has reached dangerous levels, potentially 2.1 times capacity. TEPCO has lost control of pressure at a second unit, raising concerns about safety and management accountability. The reactor is currently off but continues to produce decay heat, necessitating cooling to prevent a meltdown. There are conflicting reports about an explosion, with indications that it may have originated from a buildup of hydrogen around the containment vessel. The situation remains serious, and TEPCO plans to flood the containment vessel with seawater as a cooling measure.
  • #8,251
It was pretty much get out any way you could, and run away.
That's the rational human response to what appears at the time to be a life-threatening event.
Nuclear power stations ought to be designed to be safe whenever all the staff unexpectedly rush for the exit and the electricity supply fails. How many of the world's power plants fit that?
 
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  • #8,252
NUCENG said:
US BWRs I am familiar with have pump houses to protect the cooling water pumps for General Service Water, Emergency Service Water and Circulating Water systems. These buildings are safety-related, sesmically qualified and water tight where to protect the pump motors. Impeller shafts drive the impellers through a water sealed fitting on the motor floor. Power cables can be elevatedor routed in water tight conduits. So it is possible to protect pumps from flooding damage even if they are located near the water edge.

An electric motor does not need to have contact with the atmosphere, so it is possible to create very watertight designs. For example a conventional submarine basically consists of a very watertight electric motor. Mechanical shocks caused by boats or cars or oil tanks brought by the tsunami wave could also be averted with some sort of concrete bunker.

Most Curious said:
Do the seawater pumps have a safety for loss of NPSH?

Surely they sucked air when the sea retreated in the moments before the tusnami!

You may want to have a look at my reply to a similar question at https://www.physicsforums.com/showthread.php?p=3306874#post3306874
 
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  • #8,253
biffvernon said:
That's the rational human response to what appears at the time to be a life-threatening event.
Nuclear power stations ought to be designed to be safe whenever all the staff unexpectedly rush for the exit and the electricity supply fails. How many of the world's power plants fit that?

One of the lessons learned from TMI2 was the need to control the access amd distractions in the control room. Employees and others crowded into the control room to help. They didn't run away. It was necessary to order people to leave the site. Technical Support Centers and Emergency Operating Facilities have been put in place outside the control room on site and off site respectively. These facilities have dedicated communications and monitoring systems. The EOF has specific provisions for the media, Links to regulators, police, emergency response providers and local and state government are provided. These groups feed recommendations and support to the control room with less noise, congestion, and distraction.
 
  • #8,254
NUCENG said:
This report is a verbatim quote from other news reports. My first criticism is the description of a 3 cm or 7 cm fault. A linear crack is not a significant leak. Leakage requires a differential pressure AND a break AREA. If this is a newsperson misquote and the answer is 3 cm2 or 7 cm2 that is way less than the area that would be classified as containment failure.

Tepco said if it hypothesizes that a breach of about 3 cm wide occurred at the reactor 1 containment vessel 18 hours after the quake and widened to about 7 cm 50 hours later
http://search.japantimes.co.jp/cgi-bin/nn20110526a1.html

Seems to me that if there is a crack that is 7cm wide (not long, but wide) that would make the opening at least ~40cm2. Its worth noting that this is a hypothesis by Tepco to explain the various instrument readings from the reactor, so they probably have a particular flow-rate in mind for the theoretical leak.

"If we do our analysis on the premise that there was a leak in the piping, it matches (data) in reality," a Tepco official said at a news conference.
 
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  • #8,255
What is with unit 2 sfp ? They can't fill it with water, size is the same like in unit 4, but in unit 4 after injection water level is ~6400mm, in unit 2 (after injestion) only ~3500mm, also the temperature jumps are strange, maybe sensor damage ? Temperature is bigger after water injection...
for example
5/22 11:00 2000mm 46C
5/23 05:00 4000mm 70C
5/26 05:00 3000mm 45C
 
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  • #8,256
biffvernon said:
That's the rational human response to what appears at the time to be a life-threatening event.
Nuclear power stations ought to be designed to be safe whenever all the staff unexpectedly rush for the exit and the electricity supply fails. How many of the world's power plants fit that?

Many. Most, in fact. Nuclear plants are the exception, really. Anyway, even these reactors can scram all by themselves and keep cool automatically for as long as power and water is available. The operators are there to finesse things like fuel consumption and respond to emergencies... just like in an airliner.

One stupid difference from an airliner is they can't generate electricity for themselves. It would be trivial to retrofit. You could patch a derivation and a small steam turbine in anyone of the existing circuits. You could put three of them in just to be sure, make one run off steam coming out from that emergency pressure valve that vents to the outside air. It could do double duty as a nice, apocaliptically loud evacuation siren if you dimension it properly.
 
  • #8,257
WhoWee said:
About 7,000(?) posts ago I also pondered the possibility of a mechanical backup. It seems reasonable something could operate off the excess heat - like a giant thermostat - to open and let sea/fresh water in - then close when the temperature drops?
All this is about the design basis. Of course it's possible to design more systems, pools, heat exchangers, cooling towers but first you have to set up your design basis. Then if something bad happens you can check if it was an error in build, in design or in design basis.
 
  • #8,258
NUCENG said:
Each of the plants has three circulating water pumps (Unit 1 may only have 2). Those are the largest pumps in your pictures. Each plant probably also has two general service water pumps and two emergency service water pumps. If you look at Unit 4 you see the four small pumps and three circular areas at the inlet that are where the motors for the circulating water pumps should be. Since the plant was in an outage the motors may have been removed for maintenance. Or they may have been destroyed in the tsunami.

Yesterday I found a Tepco report confirming that unit 4's 3 main seawater pumps were removed for maintenance : https://www.physicsforums.com/showthread.php?p=3321704#post3321704

What is the purpose of "service water pumps" ?

jlduh said:
I add a picture showing how they look like -these are from N°5 reactor and got hit by this big blue structure, but they look similar to the others:

http://www.netimago.com/image_202944.html

The trajectory of the big blue structure, a gantry crane, is shown on page 40 of http://www.tepco.co.jp/nu/fukushima-np/images/handouts_110525_01-j.pdf. I guess this is the crane that is used, among other purposes, when the pumps are removed for maintenance.

English version is now available at http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110525_01-e.pdf
 
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  • #8,259
tsutsuji said:
Yesterday I found a Tepco report confirming that unit 4's 3 main seawater pumps were removed for maintenance : https://www.physicsforums.com/showthread.php?p=3321704#post3321704

What is the purpose of "service water pumps" ?



The trajectory of the big blue structure, a gantry crane, is shown on page 40 of http://www.tepco.co.jp/nu/fukushima-np/images/handouts_110525_01-j.pdf. I guess this is the crane that is used, among other purposes, when the pumps are removed for maintenance.

General service water pumps feed non-safety coolers/ Emergency service water feeds the safety related coolers such as the diesels.
 
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  • #8,260
NUCENG said:
General service water pumps feed non-safety coolers/ Emergency service water feeds the safety related coolers such as the diesels.

Thanks. The two safety-related ones are probably those belonging to the 12 (=6 units x 2) failed "RHR sea water systems" mentioned on page 50 of http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110525_01-e.pdf
 
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  • #8,261
seeyouaunty said:
http://search.japantimes.co.jp/cgi-bin/nn20110526a1.html

Seems to me that if there is a crack that is 7cm wide (not long, but wide) that would make the opening at least ~40cm2. Its worth noting that this is a hypothesis by Tepco to explain the various instrument readings from the reactor, so they probably have a particular flow-rate in mind for the theoretical leak.

That is about 1/4 the size of leakage expected in: http://www.osti.gov/bridge/servlets/purl/5630475-EX87x5/5630475.pdf.

That would be considered leakage, not containment failure. Are they fitting the data to their theories or developing their theories to fit the data? I think the containment pressure and temperature conditions reached in unit 1 almost guarantee more leakage than that.
 
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  • #8,262
jlduh said:
Do we know more on this for the various reactors/plants? Which pumps did fail?

These pumps should at least be put in a bunker if they have to stay close to the sea...

At Daini, from the picture i posted, i don't see the main pumps being inside a building. This picture is from the 12th of March, one day after the tsunami.
[PLAIN]http://www2.jnes.go.jp/atom-db/en/trouble/individ/power/g/g20051102/051102.gif
Diagram for Fukushima Daini unit 2, taken from http://www2.jnes.go.jp/atom-db/en/trouble/individ/power/g/g20051102/news.html

On page 46 of http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110525_01-e.pdf the building by the sea is called "heat exchanger building". This raises the possibility that the building was not built in order to provide tsunami protection, but in order to provide housing for the heat exchanger(s) of the RHR and Diesel generator systems.
 
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  • #8,263
Astronuc said:
It's been years since I've done a calculation on the turbine side, but I remember a vacuum drawn on the condenser since the water temperature is cold (relative to the turbine) and the vapor pressure is very low - less the 1 atm. That water would be passed to the reheaters coming off the LP stages.

Typical pressure in a BWR condenser is a few tens of millibars (abs), i.e. rather good vacuum. Loss of vacuum (absolute pressure 0.2 - 0.3 bar) results in a turbine trip. In order to maintain vacuum, a constant suction is needed due to accumulating hydrolysis gases, which are transferred through recombiners to the off-gas system and eventually to the exhaust stack.
 
  • #8,264
tsutsuji said:
Thanks. The two safety-related ones are probably those belonging to the 12 (=6 units x 2) failed "RHR sea water systems" mentioned on page 50 of http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110525_01-e.pdf

I agree. A rose by another name. One of the safety loads for each pump is likely the RHR (A or B) heat exchanger which is an ECCS component.
 
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  • #8,265
zapperzero said:
http://www.japantoday.com/category/national/view/japan-ends-projections-of-radioactive-substance-spread-from-nuclear-plant

1 Bq per 72 hours of I131? We wish! Obviously the reporter dropped a few orders of magnitude.
 
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  • #8,266
http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110526_01-e.pdf"
 
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  • #8,267
NUCENG said:
1 Bq per 72 hours of I131? We wish! Obviously the reporter dropped a few orders of magnitude.

Isn't that probably well below the radioactivity release of an normally operating NPP? Just wondering...
 
  • #8,268
clancy688 said:
Isn't that probably well below the radioactivity release of an normally operating NPP? Just wondering...

TThat is about 2% of the decay rate of potassium in a banana. ;-}
 
  • #8,269
NUCENG said:
That would be considered leakage, not containment failure.

Were is the border between leakage and containment failure?
To my understanding something that leaks does not contain.
 
  • #8,270
NUCENG said:
TThat is about 2% of the decay rate of potassium in a banana. ;-}

Oh boy, I'll never eat bananas again. Only using them for irradiating food. =D

---------------------------------------------------------------------------

And new infos from EX-SKF again.

http://ex-skf.blogspot.com/2011/05/fukushima-i-nuke-plant-reactor-1-rpv.html

Today, TEPCO admits the Reactor 1's Reactor Pressure Vessel (RPV) may have broken right after the earthquake and the pipe connected to the High Pressure Coolant Injection system (HPCI) for the Reactor 3 probably also broke during the earthquake. (The article linked below doesn't say the piping is for the HPCI, but the earlier Mainichi Japanese article on May 25 says so.)

A diagram showing temperature changes at the reactor's containment vessel indicates that temperatures and pressure momentarily shot up immediately after the quake.

Mitsuhiko Tanaka, a former nuclear reactor design engineer, says high-temperature steam apparently leaked out to the containment vessel after either the reactor's pressure vessel or its accessory piping was partially damaged.

The operator, Tokyo Electric Power Co., admitted Wednesday that critical cooling piping at the same plant's No. 3 reactor may also have been damaged in the quake.
 
  • #8,271
NUCENG said:
US BWRs I am familiar with have pump houses to protect the cooling water pumps for General Service Water, Emergency Service Water and Circulating Water systems. These buildings are safety-related, sesmically qualified and water tight where to protect the pump motors. Impeller shafts drive the impellers through a water sealed fitting on the motor floor. Power cables can be elevatedor routed in water tight conduits. So it is possible to protect pumps from flooding damage even if they are located near the water edge.

Fascinating information. Thanks for sharing.

Which US BWRs would it be that you're familiar with?

Are there any references for us to better understand the details of the characteristics you described? It would be great to have a source we could quote, but of course I understand that you may have been simply describing from memories of personal experience.

Do you know how they handle cooling with these huge (1,000~kW?) motors running in these hardened buildings?
 
  • #8,272
  • #8,273
elektrownik said:
What is with unit 2 sfp ? They can't fill it with water, size is the same like in unit 4, but in unit 4 after injection water level is ~6400mm, in unit 2 (after injestion) only ~3500mm, also the temperature jumps are strange, maybe sensor damage ? Temperature is bigger after water injection...
for example
5/22 11:00 2000mm 46C
5/23 05:00 4000mm 70C
5/26 05:00 3000mm 45C

This is not water level in the SFP, but in the FPC skimmer tank. If this level increases, it simply tells that SFP is full. Otherwise, no conclusion can be drawn.
 
  • #8,274
I have been lurking for a while (this is about the only place on the net where a meaningful discussion takes place) and i figured you guys might be interested in this:

---
A meltdown occurred at one of the reactors at the Fukushima No. 1 Nuclear Power Plant three and a half hours after its cooling system started malfunctioning, according to the result of a simulation using "severe accident" analyzing software developed by the Idaho National Laboratory.

Chris Allison, who had actually developed the analysis and simulation software, ...
---
http://mdn.mainichi.jp/mdnnews/news/20110523p2a00m0na019000c.html
 
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  • #8,275
NUCENG said:
During BWR plant operation there are areas that get to 1 Sv per hour primarily near steam piping due to N-16 gamma radiation. These areas are locked high radiation errors where personnel access is not allowed during operation. Examples include the steam jet air ejector area, the reactor water cleanup area, and the steam tunnel between the reactor building and turbine building.

With a 16 second half life, I'm guessing the radiation is not coming from the N-16. After all the time that's passed, I'd guess the least bad scenario would be one of the Cs isotopes.
(thread regarding the radioactive pile of rubble, in case anyone is wondering)
 
  • #8,276
NUCENG said:
US BWRs I am familiar with have pump houses to protect the cooling water pumps for General Service Water, Emergency Service Water and Circulating Water systems. These buildings are safety-related, sesmically qualified and water tight where to protect the pump motors. Impeller shafts drive the impellers through a water sealed fitting on the motor floor. Power cables can be elevatedor routed in water tight conduits. So it is possible to protect pumps from flooding damage even if they are located near the water edge.

Thanks for the details. The question is:

it's possible to protect them (resistant to tsunami may be tougher though?), but was it the case, and is it the case everywhere on a so critical part of the nuke plants?

Also, what about the risks of damaging the impellers/shafts loads during water hammering? The longer an axis is, the weaker it is in case of tsunami hit.
 
  • #8,277
Isn't there something strange with the diagrams page 53 of http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_110525_01-e.pdf ?

First I am surprised to learn about a new difference between Fukushima Daiichi and Fukushima Daini, with the presence of an additional cooling loop and heat-exchanger between the diesel engine and the sea at Daini.

What about the air-cooled diesel generators at Fukushima Daiichi units 2,4,6 ? Why should they need a heat-exchanger (between two liquids coolants? oil and water ?) in addition to the radiator ?
 
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  • #8,278
In case it was not already known , one of the three diesel generators at Tokai NPP failed after tsunami hit. IAEA is going to investigate.

http://mdn.mainichi.jp/mdnnews/news/20110526p2a00m0na010000c.html
 
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  • #8,279
Rive said:
This also imply the possibility of direct release from an RPV (or less likely from an SFP): otherwise it would be trapped in the torus.

TEPCO admits to having performed dry venting of the No 2 pressure vessel on 15Mar.

I assume "dry venting" indicates that the RPV was vented to atmosphere without traveling through the wet filtration of the torus.

http://search.japantimes.co.jp/cgi-bin/nn20110330a3.html"
 
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  • #8,280
NUCENG said:
Again, I am not saying there wasn't seismic damage. there were reports of water leakage inside reactor buildings, but apparently it was not radioactive as some workers feared. Unit 3 had a fairly significant delay before starting RCIC or HPCI and there is no clear explanation why. But both systems were used later. There was speculation that the Unit 1 Isolation Condenser failed due to sesmic damage, but now it appears that was operator action that secured the system after only a few minutes. I just haven't seen any conclusive evidence of safety system failures prior to the tsunami.

There is this statement that Tepco workers entered the building N°1 during the night and the building was full of steam with measurement around 300 mSv/h. I agree that this was during the night of the 11-12 th of March (so after tsunami ), that Tepco press releases on their site does not mention this AFAIK, and that it is very possible that at this time, there was already significant damage on the core from the loss of coolant event (this new american study talking about a few hours for meltdown, which was by the way i think the order of magnitude of the severe accident study on BWR done I think in 1979 (?)).

So this doesn't prove clearly that it was from earthquake, i agree. But it may be an element to take into account.
 

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