Japan Earthquake: Nuclear Plants at Fukushima Daiichi

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Discussion Overview

The discussion revolves around the technical aspects and current status of the nuclear plants at Fukushima Daiichi following the earthquake and tsunami in Japan. Participants are seeking reliable information regarding the operational conditions, safety measures, and potential risks associated with the nuclear reactors in the aftermath of the disaster.

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested

Main Points Raised

  • Some participants express skepticism about the reliability of media reports and emphasize the need for technical information from official sources like TEPCO and METI.
  • There are concerns regarding the reactor pressure levels, with reports suggesting that pressure may have exceeded safe limits, which some participants describe as a significant issue.
  • Questions are raised about the likelihood of a meltdown, with differing opinions on whether this is a realistic concern or media exaggeration.
  • One participant explains the role of coolant in a nuclear power plant, noting that it is essential for cooling the reactor and managing decay heat after shutdown.
  • There is discussion about the reactor's ability to be scrammed (shut down) and the implications of losing coolant, with some participants clarifying that decay heat continues to be produced even after shutdown.
  • Concerns are raised about the explosion of the containment building and its implications for safety, with speculation about the potential release of radioactive materials.
  • Participants discuss the wind direction at the time of the explosion and its potential impact on the dispersion of any radioactive materials released.

Areas of Agreement / Disagreement

Participants do not reach a consensus on the likelihood of a meltdown or the implications of the current situation at Fukushima Daiichi. There are multiple competing views regarding the severity of the situation and the reliability of information being reported.

Contextual Notes

Participants note the limitations of available information, including the reliance on second-hand reports and the challenges in verifying the status of the reactors and containment structures. There are also unresolved questions regarding the operational status of safety systems and the exact nature of the explosion.

  • #12,331
One thing I don't understand is how the amount of water has been multiplied 6x over February but there has been no change in the reactor water level. Is the gauge broken, is the water evaporating quicker or is the water escaping the reactor?
 
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  • #12,332
Gaffney said:
One thing I don't understand is how the amount of water has been multiplied 6x over February but there has been no change in the reactor water level. Is the gauge broken, is the water evaporating quicker or is the water escaping the reactor?
I think that this is the case.
 
  • #12,333
Yes, there is absolutely no change. Either the gauge is broken, or there is a leak at this level, letting escape even the big amount of water they are adding now.
 
  • #12,334
Yamanote said:
It also makes me wonder, why Tepco pays so much attention to this temperature sensor

Regardless of what is happening, imagine the wave of criticism they would face if they ignore it.
 
  • #12,335
The main circulation pump seals have certainly leaked since mid-March, and if there's any hole in the shroud, water from the core region will escape that way. In addition, there most probably are holes in the RPV bottom penetrations caused either by molten core material or corrosion.

But as far as I know, we still haven't been told which pressure measurement locations the reported level measurement is actually based on.
 
  • #12,336
Borek said:
Regardless of what is happening, imagine the wave of criticism they would face if they ignore it.

You are right Borek and I really appreciate their precaution this time. So let's hope for the best.
 
  • #12,337
Gaffney said:
One thing I don't understand is how the amount of water has been multiplied 6x over February but there has been no change in the reactor water level. Is the gauge broken, is the water evaporating quicker or is the water escaping the reactor?

Seen that the water level in the reactor was too low to be seen by the borescope, one can assume the RPV has some leaks, maybe large ones and that any reported reactor water level may be invalid. Obviously the increased injections will gradually raise the water level in the plant basement, but with 80,000 cubic meters there already, it will take some time to make a substantial increase.
The JAIF used to publish daily, then weekly situation reports that included the water levels in the various parts of the facility, but that stopped about a month ago when a more generic summary was substituted. TEPCO was the source of their data, so it may still be available there if one knows where to look.
 
  • #12,338
etudiant said:
TEPCO was the source of their data, so it may still be available there if one knows where to look.

If this is what you mean:

-> http://www.tepco.co.jp/en/nu/fukushima-np/index-e.html

-> Scroll down to "Situation of water level, transfer and treatment of the accumulated water"

This information is also provided with the daily press conference report and every now and then there is a more detailed report:

http://www.tepco.co.jp/en/press/corp-com/release/betu12_e/images/120201e3.pdf
 
  • #12,339
elektrownik said:
Unit 2 sensor is damaged because it is 250+ C now, and it is impossible
is it possible that the water boiled/drained away?
 
  • #12,340
Yamanote said:
If this is what you mean:

-> http://www.tepco.co.jp/en/nu/fukushima-np/index-e.html

-> Scroll down to "Situation of water level, transfer and treatment of the accumulated water"

This information is also provided with the daily press conference report and every now and then there is a more detailed report:

http://www.tepco.co.jp/en/press/corp-com/release/betu12_e/images/120201e3.pdf

Thank you, that is exactly what I was thinking of.
A very helpful reference that also gives some insight into the functioning of the water decontamination effort.
 
  • #12,341
jim hardy said:
Anyhow don't bet a lot of money or invest much worry on a lone thermocouple that's suffered the abuse those have. But keep an eye on it.

It's great info from you as usual, jim. But it makes it sound to me as if the other thermocouples failing too is pretty much a given.
 
  • #12,342
Strange temps in unit 2 (data from today):
 

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  • #12,343
elektrownik said:
Strange temps in unit 2 (data from today):

More sensors on the fritz? Maybe because of the extra water?
 
  • #12,344
elektrownik said:
Strange temps in unit 2 (data from today):

Is a melt-through possible?
 
  • #12,345
Interesting that all strange temperature data are from bottom of RPV or close to this part of RPV so it is possible that something bad is in progress.
 
  • #12,346
Multiple sensors trending together is worrisome.

But do i see readings of 118, 251 and 4 ?
Those need to be cross checked against other indications such as visible steam, temperature and particulate analysis of air exiting building.

and ask the technnicians whether those tc's are wet.
 
  • #12,347
Borek said:
I have not followed the situation for a long time, so I am not sure about details. What pressures are we talking about? Temperature shouldn't go above boiling point, 276℃ means boiling unless pressure is over 60 atm.

I'm guessing it will be difficult to pressurize that RPV much above one atmosphere. And if the TC is away from water, there need not be any pressure.
 
  • #12,348
swl said:
I'm guessing it will be difficult to pressurize that RPV much above one atmosphere.

That's what I was aiming at - as the pressure is unlikely to be that high, if the sensor is under water it must be wrong.

And if the TC is away from water, there need not be any pressure.

Yes, but what is the water level and is the TC under water or above? Or do we simply not know?
 
  • #12,349
http://www3.nhk.or.jp/news/genpatsu-fukushima/20120214/1350_ondokei.html The NISA instructed Tepco to write a report by 15 February, on such things as the cause of the high thermometer values and the way to measure temperatures by other methods.

http://www.mbs.jp/news/jnn_4953273_zen.shtml Tepco tested 15 of the 41 thermometers installed inside unit 2's PCV, and found that two more thermometers were broken. Nothing abnormal was found with the two thermometers located at the same height as the one that had abnormal values.

http://www.47news.jp/CN/201202/CN2012021401002271.html 8 thermometers are broken out of a total of 41 at unit 2's RPV. Adding to the thermometer that momentarily reached 400°C, two other thermometers were found with an abnormal electric resistance. Tepco had judged that 5 other thermometers were broken. Tepco is judging the RPV's temperature trend with the remaining 33 thermometers.
 
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  • #12,351
  • #12,352
tsutsuji said:
These results are hardly different from those of 6 February, are they?

Right. That's why I ignore all the stuff on enenews.
 
  • #12,353
Yamanote said:
Right. That's why I ignore all the stuff on enenews.

Well, ENENews has been in the forefront of the disaster focused reporting, so they deserve to be taken with more than a pinch of salt.
That said, we've not had afaik a nuclear reactor of this size experience as catastrophic a failure, so Fukushima is writing new chapters in the book.
The layman's understanding is that there is no plausible mechanism to achieve recriticality in the damaged fuel, but that residual decay heat is a serious issue. Is this incorrect and are there plausible ways the damaged fuel can be brought back to criticality in any substantial way as a consequence of this accident?
 
  • #12,354
etudiant said:
The layman's understanding is that there is no plausible mechanism to achieve recriticality in the damaged fuel, but that residual decay heat is a serious issue. Is this incorrect and are there plausible ways the damaged fuel can be brought back to criticality in any substantial way as a consequence of this accident?
ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/09-sara.pdf

So they think it's likely happens in some circumstances.

But Tsutsuji is right about the Xenon levels, so in this particular case it's not likely happened.
 
  • #12,355
Thanks Rive, very interesting!

Enenews compares two different measurement anyway...
So they seem to be more into headlines than into explanations and solutions. Not helpful to me.
 
  • #12,356
Rive said:
ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/09-sara.pdf

So they think it's likely happens in some circumstances.

But Tsutsuji is right about the Xenon levels, so in this particular case it's not likely happened.

Thank you, Rive, for a useful link.
This is an informative study, but dealing with a much lesser accident than Fukushima.
They posit a situation after an accident where the control rods have melted but the fuel is largely intact, and resume cooling water injections with unborated water. Obviously the fuel geometries maximize the neutron capture once the water moderates the neutrons emitted.
Here we have damaged/destroyed fuel, maybe in heaps, maybe melted into corium, under a shower of borated water, so we have fast neutrons, with no moderator around and bad geometries.
How is recriticality possible in those conditions?
 
  • #12,357
etudiant said:
They posit a situation after an accident where the control rods have melted but the fuel is largely intact, and resume cooling water injections with unborated water. Obviously the fuel geometries maximize the neutron capture once the water moderates the neutrons emitted.
Here we have damaged/destroyed fuel, maybe in heaps, maybe melted into corium, under a shower of borated water, so we have fast neutrons, with no moderator around and bad geometries. How is recriticality possible in those conditions?

How about this paper - it seems to me to better match the current situation, although apologies in advance if I have missed something obvious. They suggest that based on a simulation similar to three mile island, cycling criticality events are quite possible in a damaged fuel debris bed, although they conclude that they should be self-regulating and not large enough to destroy the containment (average 5-7GJ):

"Recriticality Energetic of a Hypothetical Water Reflood Accident in a Damaged Light Water Reactor"

http://www.osti.gov/bridge/purl.cover.jsp?purl=/16911-VGVXER/webviewable/

As far as the boration is concerned, if the water is flowing through the primary containment like a sieve at many tons per hour, I can not see how sporadically injecting large amounts of boron would maintain any kind of stable boration - I think the media people have misread the boron injections.

During the last injection of boron, the TEPCO daily update hinted that their motivation was actually that by rapidly increasing the injection rate they might raise the level of the water in the reactor and reflood a damaged section of the core and inadvertently increase reactivity:

http://www.tepco.co.jp/en/press/corp-com/release/12020805-e.html

"In order to avoid the increasing
possibility of re-criticality to occur, which might be brought up by
sudden cold water injection, resulting in the rise of water density
inside the reactor, we injected boric acid into the reactor as a safety
countermeasures against the re-criticality from 0:19 am to 3:20 am on
February 7, which was before increasing the amount of injection water,
and changed the amount of the core spray system injection water from 3.7
m3/h to 6.7m3/h at 4:24 am (the amount of the continuing feed water
system injection is 6.8m3/h)."

So rather than temp going up -> better add boron, it seems like temp going up -> better increase water injection -> better borate reflood water in case more reactive fuel is flooded. Looking at it that way, the boron injections suddenly seem less knee-jerk.
 
  • #12,358
Jim Lagerfeld said:
How about this paper - it seems to me to better match the current situation, although apologies in advance if I have missed something obvious. They suggest that based on a simulation similar to three mile island, cycling criticality events are quite possible in a damaged fuel debris bed, although they conclude that they should be self-regulating and not large enough to destroy the containment (average 5-7GJ):

"Recriticality Energetic of a Hypothetical Water Reflood Accident in a Damaged Light Water Reactor"

http://www.osti.gov/bridge/purl.cover.jsp?purl=/16911-VGVXER/webviewable/

As far as the boration is concerned, if the water is flowing through the primary containment like a sieve at many tons per hour, I can not see how sporadically injecting large amounts of boron would maintain any kind of stable boration - I think the media people have misread the boron injections.

During the last injection of boron, the TEPCO daily update hinted that their motivation was actually that by rapidly increasing the injection rate they might raise the level of the water in the reactor and reflood a damaged section of the core and inadvertently increase reactivity:

http://www.tepco.co.jp/en/press/corp-com/release/12020805-e.html

"In order to avoid the increasing
possibility of re-criticality to occur, which might be brought up by
sudden cold water injection, resulting in the rise of water density
inside the reactor, we injected boric acid into the reactor as a safety
countermeasures against the re-criticality from 0:19 am to 3:20 am on
February 7, which was before increasing the amount of injection water,
and changed the amount of the core spray system injection water from 3.7
m3/h to 6.7m3/h at 4:24 am (the amount of the continuing feed water
system injection is 6.8m3/h)."

So rather than temp going up -> better add boron, it seems like temp going up -> better increase water injection -> better borate reflood water in case more reactive fuel is flooded. Looking at it that way, the boron injections suddenly seem less knee-jerk.

Thank you for a very relevant insight.
This paper certainly seems to fit the bill pretty well. It suggests that recovering the fuel with water has in fact quite a powerful impact on the potential for criticality, which is certainly news to me. That implies that the future performance of this facility is in fact somewhat unpredictable, rather than being bounded by the decay heat curve. It also means that getting a good handle on the distribution and location of the fuel in these reactors is of more than academic importance.
 
  • #12,359
etudiant said:
It also means that getting a good handle on the distribution and location of the fuel in these reactors is of more than academic importance.

Yes.
There was a large thread about the topic "what caused the explosion of reactor 3" or the like which got deleted by the moderators.

My impression is that this happened because this thread threatened to become blasphemic in the way that it could show that recriticality issues are in fact possible.

It showed the neutral and attentive reader the thinking taboos of the nuclear "professionals".
I remember the <edit> user "Morbius" multiply stating apodictically that a recriticality would be impossible, implying that the corium is present in the form of one big, contiguous blob and basing his "calculations" on this assumption.
Three Mile Island proved that this is unlikely, but this belief appears to be still firm at most nuclear "professionals".

The user "Jim Hardy" pointed several times to the fact that he considers reflooding a reactor that has run dry as a very dangerous thing.
How true, as the control/absorber rods are going to melt away long before the fuel rods, and the water moderator would fill that void and create the risk of an uncontrolled chain reaction.
But nobody seemed to understand what "Jim Hardy" shyly pointed at and there was no discussion about this problem.

Anyway, can we really exclude the possibility that the "reordering" of the corium particles due to the changes of the cooling by Tepco could create critical configurations when they randomly form "lattices" of fuel material and moderating water?
The fact Tepco felt the need to use boron again proves that they are actually concerned.

I know that what I said is pure blasphemy to some nuclear "professionals".

But can their over-simplified models like MELCOR, MAAP etc really cope with the complex reality in an actual core-melt situation and its aftermath?

These models grossly failed already at analyzing the Three Mile Island event.
So, should we sheeple still believe and trust in models the nuclear industry propagates even though they have been proven to be inadequate since decades?

I would really appreciate if there would be a discussion that goes beyond some particular dogmata like the categoric stating that (re)critical configurations would be impossible, towards a discussion that tries to find out what configurations could possibility lead to re-criticality, and then to find out how to avoid such configurations occurring.
This would be way more constructive than that flaming I am used from some residents here.
 
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  • #12,360
I was an avid participant in that discussion.

Atomfritz said:
Yes.
There was a large thread about the topic "what caused the explosion of reactor 3" or the like which got deleted by the moderators.
My impression is that this happened because this thread threatened to become blasphemic in the way that it could show that recriticality issues are in fact possible.

Afaik the thread got locked for cleanup, there was a rash of trolling and hyperventilating n00bs near the end.

It showed the neutral and attentive reader the thinking taboos of the nuclear "professionals".
I remember the <edit> user "Morbius" multiply stating apodictically that a recriticality would be impossible, implying that the corium is present in the form of one big, contiguous blob and basing his "calculations" on this assumption.
Three Mile Island proved that this is unlikely, but this belief appears to be still firm at most nuclear "professionals".
Morbius is a bomb-maker. He doesn't really do (or indeed grok) slow-neutron, moderated criticality stuff. His area of expertise is with reflectors and neutron initiators and high keff reactions in highly enriched material. Understandable bias.

The user "Jim Hardy" pointed several times to the fact that he considers reflooding a reactor that has run dry as a very dangerous thing.
How true, as the control/absorber rods are going to melt away long before the fuel rods, and the water moderator would fill that void and create the risk of an uncontrolled chain reaction.
But nobody seemed to understand what "Jim Hardy" shyly pointed at and there was no discussion about this problem.
I understood. Debris beds look a lot like working reactors - a roughly 50/50 mix of solids and water, in a steel can. Worse, the metal (structural steel, control blades etc) separates from the oxide (the contents of the fuel rods, basically) during the melt formation phase.

Anyway, can we really exclude the possibility that the "reordering" of the corium particles due to the changes of the cooling by Tepco could create critical configurations when they randomly form "lattices" of fuel material and moderating water?
Not in my opinion.

The fact Tepco felt the need to use boron again proves that they are actually concerned.
Yes, which is why I, just as yourself, find the insistence that it can't happen faintly ridiculous. It is not happening now, though, or there would be Xe and I and other fission products released again.
 
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