Fukushima Japan Earthquake: nuclear plants Fukushima part 2

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A magnitude-5.3 earthquake struck Fukushima, Japan, prompting concerns due to its proximity to the damaged nuclear power plant from the 2011 disaster. The U.S. Geological Survey reported the quake occurred at a depth of about 13 miles, but no tsunami warning was issued. Discussions in the forum highlighted ongoing issues with tank leaks at the plant, with TEPCO discovering loosened bolts and corrosion, complicating monitoring efforts. There are plans for fuel removal from Unit 4, but similar structures will be needed for Units 1 and 3 to ensure safe decontamination. The forum also addressed the need for improved groundwater management and the establishment of a specialist team to tackle contamination risks.
  • #1,111
Hi Charles, welcome and thank you. FYI I am no specialist, I just follow the progress in Fukushima plant with a personal interest, and post translations of some stuff from Tepco and other sites, which is released mainly in Japanese language. I am most grateful to all the knowledgeable people who contribute to these pages.

Pages 38-39 in this forum contain several posts (see #756~...) that relate to your question.

Edit:
Tepco has just released this info
http://www.tepco.co.jp/nu/fukushima-np/handouts/2017/images1/handouts_170207_04-j.pdf (in Japanese)
As they were checking the "sediment cleaning device" before inserting it and guiding it onto the CRD rails, they discovered that the pump that is supposed to provide the high pressure water to the device was not working. The pump will be replaced with a similar one and they will do that cleaning test when all works fine.
 
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  • #1,113
Charles Smalls said:
So much great information on this thread. Hi Sotan, thanks for all of your effort, I have been quietly reading your contributions for so long now. Decided to make an account just to thank you and everybody else for your coverage on this.

One question about this temperature thing, before I go back to lurking; I have read that it can take up to 5 years after a reactor shuts down until the decay heat levels in the fuel reduce enough to let it be air cooled. Does anyone know how accurate that is and how it would apply to fuel in a solidified mass rather than the normal 'good configuration' where it is in separated bundles?

Many thanks to all you guys again.

For fuel that still has normal configuration, BWR fuel is air coolable in 4 months and PWR fuel at 11 months according to studies headed by the us nuclear regulatory commission.

Being in a non standard configuration would likely reduce surface area and reduce heat transfer.
 
  • #1,114
Anyone able to edit the Wikipedia page? The last phrase of this paragraph especially...

2017 radiation spike

On 3 February, 2017, several news agencies reported a significant spike in radiation levels from Reactor #2, peaking at 530 sieverts per hour, the highest level recorded since the March 11, 2011 incident. [37]These levels were announced by TEPCO, the utility company that oversees the Fukushima reactors.[36] The previous high was 73 sieverts per hour, in 2011. TEPCO believes the spike may be caused by melted nuclear fuel burning through the bottom of the containment.[35]
 
  • #1,115
Sotan said:
Anyone able to edit the Wikipedia page? The last phrase of this paragraph especially...
i tried

but it didn't take and i got a warning about blanking pages. oh well.
 
  • #1,117
Sotan said:
Anyone able to edit the Wikipedia page? The last phrase of this paragraph especially...

2017 radiation spike

On 3 February, 2017, several news agencies reported a significant spike in radiation levels from Reactor #2, peaking at 530 sieverts per hour, the highest level recorded since the March 11, 2011 incident. [37]These levels were announced by TEPCO, the utility company that oversees the Fukushima reactors.[36] The previous high was 73 sieverts per hour, in 2011. TEPCO believes the spike may be caused by melted nuclear fuel burning through the bottom of the containment.[35]

I took care of it. I'm horrible with Wikipedia though. There probably needs to be a new section about the findings from the Pcv inspection and a screen shot of the spliced images of the grating melt. I'll try to do these later if I get my computer set up again. But if someone else wants to do it that would be great.

Edit: another use keeps changing it. Not sure how to proceed
 
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  • #1,118
Hiddencamper said:
For fuel that still has normal configuration, BWR fuel is air coolable in 4 months and PWR fuel at 11 months according to studies headed by the us nuclear regulatory commission.

Being in a non standard configuration would likely reduce surface area and reduce heat transfer.

Hi Hiddencamper, thank you too for so much valuable insight.

The fuel cooling subject is an interesting one. My tutor was talking about surface area and heat transfer comparing french fries to a baked potato and it brought me to thinking about the reactor fuel melts. The mass must have different retention properties compared to the bundles. On the other hand, I really had no idea there was such a difference between BWR and PWR fuel heat decays or that either would be so short.

https://www.nrc.gov/waste/spent-fuel-storage/faqs.html

The NRC website on the above page quotes a more typical wet storage time frame of 3-5 years before transferring to dry casks. Is the additional time to allow the fuel to 'cool' radioactively as well as thermally or just good operating procedure?
 
  • #1,119
Charles Smalls said:
Hi Hiddencamper, thank you too for so much valuable insight.

The fuel cooling subject is an interesting one. My tutor was talking about surface area and heat transfer comparing french fries to a baked potato and it brought me to thinking about the reactor fuel melts. The mass must have different retention properties compared to the bundles. On the other hand, I really had no idea there was such a difference between BWR and PWR fuel heat decays or that either would be so short.

https://www.nrc.gov/waste/spent-fuel-storage/faqs.html

The NRC website on the above page quotes a more typical wet storage time frame of 3-5 years before transferring to dry casks. Is the additional time to allow the fuel to 'cool' radioactively as well as thermally or just good operating procedure?

The difference between PWR and BWR fuel has to do with power density. Due to lower heat transfer in BWRs because of boiling, a BWR core needs 3-4 times as many fuel assemblies to have the same power output as a PWR.

As for the duration, the 3-5 years is because of cask safety analysis for storage casks. You can store fuel in shorter times, but you would have to put less fuel rods in the cask as a result, and that is wasteful. The casks have both local heat limits and total heat limits based on loading.
 
  • #1,120
@Hiddencamper

what little i could see of reactor bottom looked in surprisingly good shape to me.

Ours(PWR) of course had only traveling incore tube penetrations , i think not even a drain . So it was much simpler.

Did i miss sight of a lower head melt-through?

With all the seawater that went through in early days sediment is no surprise. Need a few pieces of it to analyze. Surely they've done that ?

old jim
 
  • #1,121
jim hardy said:
Need a few pieces of it to analyze. Surely they've done that ?
Not yet. They inserted a camera to check for any obstacles for the planned robot insertion. Now they first want to use a "sediment cleaning device" (don't know about sample taking capabilities) and after that the robot (which will have radiation and temperature sensors and cameras, but again no sample taking capabilities as far as I know).
 
  • #1,122
Hiddencamper said:
Edit: another use keeps changing it. Not sure how to proceed

hmmm looks better now ! was that you ?

Meanwhile , back at the reactor

??
http://www.tepco.co.jp/en/nu/fukushima-np/handouts/2017/images/handouts_170202_01-e.pdf
Fuku2BottomHead.jpg
 
  • #1,123
jim hardy said:
Need a few pieces of it to analyze. Surely they've done that ?
I don't think they should rush with that... To safely sample something from 'there' would require some serious thinking.

Ps.: As it is now I won't even try to retrieve that robot... Unintended 'sampling' would be a bad karma.
 
  • #1,124
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  • #1,126
jim hardy said:
But this patent (...) is for the magnetic Westinghouse style control rods not GE hydraulic rods.
Thanks! Those things look like chains to me, but I wouldn't know what they are for:
upload_2017-2-8_22-34-51.png


Edit: I think Tepco identifies them as part of the CRD exchanger, I wouldn't know.
 
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  • #1,127
turi said:
Thanks! Those things look like chains to me, but I wouldn't know what they are for:
View attachment 112770

Edit: I think Tepco identifies them as part of the CRD exchanger, I wouldn't know.
The images circulating from Unit 5 give a close idea of the equipment in its original state.

https://s28.postimg.org/v3qlx6esb/zoom.jpg
 
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  • #1,128
http://www.tepco.co.jp/nu/fukushima-np/handouts/2017/images1/handouts_170209_08-j.pdf (in Japanese)
Results of the first attempt to remove/clear away sediments from the CRD rails.

Page numbered 4 shows two pairs of images taken somewhere at the top of the CRD rails; the left image is taken before clearing away sediment, the right image is taken after. (Left pair is taken with guide-pipe camera, right pair is taken with the camera installed on the device itself.)

Page 4 shows another two pairs of images taken a bit lower on the slope, where the sediment is better stuck to the surface and harder to remove. Each pair contains before/after images. Left side pair is taken using the guide-pipe camera, hence the device is seen; right side pair of images are taken with the device camera.

Page 5 shows two images (one from guide-pipe camera and one from device camera) taken as the device is traveling on the sediment itself.

Page 6 - conclusions:
- they cleaned about 1m of the 5 metres they had planned to clean (not clear if the planned all 5m for one single session);
- as we move towards the pedestal, the sediment sticks more strongly to the surface and takes longer to clear away;
- they stopped the operation when visibility became bad, and retrieved the device, as they don't want to cause extra visibility troubles for the next step (inspection robot);
- the device was able to climb over and drive over the sediment but there were also places where it couldn't advance/travel over the sediment.

They will analyze the data obtained in view of deciding the next step.

Larger photos and a video (which I couldn't see yet) here:
http://photo.tepco.co.jp/date/2017/201702-j/170209-01j.html

Edit: I saw the video now. There are many fragments of the "sediment" which appear to be pieces of aluminum foil or something similar. At 1:37 the water stream peels off and overturns something that looks like a "slab" of material, maybe 1-2 cm thick, maybe 10x10 cm or more in area. Slab may not be the right word, it still looks like a pretty light material. Lots of radiation-induced noise in the video image.
 
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  • #1,129
Now I see it:

post_2.jpg
post_1.jpg
 
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  • #1,130
I watched the first part of the press conference of Tepco where they showed the "sediment removal" video.
- The image getting darker (the part above where I clumsily translated as "visibility getting worse") in fact refers to the camera itself getting tired, most likely die to the damaging effect of the high radiation on the camera sensor. The images were getting darker and darker and they had to pull the device out sooner than planned - while they still had video. The 2h lifetime is in general agreement with the evaluated radiation dose and the 1000 Sv integrated, overall radiation resistance of the camera. The inspection robot to be used in the last step will probably behave similarly, as far as the camera life time is concerned.
- They didn't put this in the PDF report for lack of time, but will be announced later: they analyzed again the radiation-induced noise in the video images and they obtained a new value fo approximately 650 Sv/h, approximately in the same area where they evaluated 530 Sv/h the other day. So if the first time they might have had some doubts about that value, this new one in the same range appears to reinforce the conclusion that there is something, not very sure where, which causes images of that region to show such dose rates. (The speaker mentioned briefly that the 530 Sv/h reported the other day has been wrongly interpreted by certain news sites abroad, as an "increase" in radiation. He underlined again that a day after stopping the nuclear reaction in the vicinity of a used fuel bundle there are probably tens of thousands of Sv/h.)
- I said above that the device was unable to "crawl" in certain areas, the reason is that the tracks allow for approximately 2 cm ground clearance, the robot can easily go over 2 cm obstacles, but the highly irregular in shape sediment sometimes has much more height. It rubs onto the belly of the robot, the tracks don't provide traction any more, so it stalls. The inspection "scorpion" robto has very similar tracks so they will have to think very well what to do next.
- There is no plan to insert a second sediment-cleaning device, they can't easily replace the camera (the device itself is contaminated too), so for now there is no plan of a second attempt.
 
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  • #1,131
Sotan said:
The 2h lifetime is in general agreement with the evaluated radiation dose and the 1000 Sv integrated, overall radiation resistance of the camera.

Thanks !

Sotan said:
there is something, not very sure where, which causes images of that region to show such dose rates.
Probably something that's been around a lot of neutrons.
I'm not jumping on the Corium bandwagon yet, a local hotspot could be a little fragment of something that got vented in first weeks.
 
  • #1,132
How would any fuel fragment wind up beneath the reactor vessel other than via a melt through?
Is not the vessel set directly on the pedestal, with access openings only from below?
 
  • #1,133
etudiant said:
How would any fuel fragment wind up beneath the reactor vessel other than via a melt through?
Is not the vessel set directly on the pedestal, with access openings only from below?

My grasp is not crystal clear
but i thought the 600 sv-ish reading was not under the vessel inside the pedestal, but in the region between the containment penetration and the pedestal .
So correct me if I'm wrong
And i believe there are pipes routed through there connecting safety valves to suppression pool in torus
and lots of other pipes connected to vessel

a fuel fragment in one of them would shine right through the pipe wall.
So the question becomes what's nearby that high radiation area ?

old jim
bwrcrosssection.jpg
 
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  • #1,134
Two questions/thoughts

Isn't the entire containment flooded with water?

If so, why isn't the water shielding the camera from the radiation?

If it is, (both underwater, and shielding is happening), then wouldn't the actual radiation source be much much higher than they are calculating?

Related question, what is the dose rate (Svr/hr) for nuclear fuel that has spent 6 years cooling?

As in, if the fuel rods had been cooling for 6 years in a spent fuel pond, how radioactive would they be?

And is this rate being measured in reactor 2 the same?
 
  • #1,135
The containment is not flooded with water.
Water at the bottom of the PCV of Unit 2 is only about 30 cm deep, as you can see on page 18 of this document.
Also, if you take a look at the videos taken by Tepco on/around the CRD rails, it's pretty clear that nothing is under water there.
As for the radiation values it's a bit of a blur because of insufficient information but "in general" the dose rates measured (indirectly, just from analysis of video images) in the PCV of unit 2 "make sense for unshielded irradiated fuel", as Hiddencamper wrote somewhere 2 pages before.
 
  • #1,136
F X said:
Isn't the entire containment flooded with water?
It can be confusing because in the very first days they tried to flood/fill up the entire containment with seawater, but they could not succeed.
They could not even correctly measure the water level that time, so finally they stopped when the water pumped in were already several times more than the amount needed to fill the containment.
Right now it is as Sotan says: the containments are not flooded, but there are some (different depth for each unit) water at the bottom.
 
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  • #1,137
Thank you, jim hardy, that diagram really helps clarify the situation.
It shows mheslep's suggestion is the more plausible, as the source is apparently some lateral distance away from the reactor.
 
  • #1,138
etudiant said:
It shows mheslep's suggestion is the more plausible, as the source is apparently some lateral distance away from the reactor.
From a couple pages back, translating from a press conference
Sotan said:
Many reporters were troubled by the numbers reported for radiation level. So (if you look in the figures for Step 4 and Step 5 in this investigaton), we insert a guide pipe through the X-6 penetration, horizontally; as soon as we get inside the PCV, there's about 50 Sv/h. We keep inserting the pipe inside, horizontally, until we reach roughly around the middle of the space between PCV wall and pedestal wall. Here, in the air, image analysis suggests 530 Sv/h (!). Then the guiding pipe bends down and goes all the way to that hole in the pedestal wall; just as we enter the pedestal space, image analysis shows 20 Sv/h.

and from another link posted by Sotan, http://www.tepco.co.jp/en/nu/fukushima-np/handouts/2017/images/handouts_170130_02-e.pdf
(orange ovals mine)
bwrcrosssection2.jpg
Thanks Sotan !

I'd guess the camera went past something small and "hot" .
 
  • #1,139
You are correct with that drawing Jim.
Tepco has already published in a report (the one given in post #1109) this drawing below, which identifies the spots for which they evaluated the radiation doses.
The blue dots numbered 1, 2, 3 are the spots where they measured (by image analysis only) 30, 530 and 20 Sv/h respectively.
1 is immediately after entering the PCV. 2 is in the air, about 2.3m from the pedestal wall. 3 is immediately after entering the pedestal.
WDLkBf6.png


Changing the subject, I came home to watch the second part of the press conference held after the "sediment clearing session"... only to find that it is not available anymore. I should have downloaded it, I guess.
 
  • #1,140
Sotan said:
Changing the subject, I came home to watch the second part of the press conference held after the "sediment clearing session"... only to find that it is not available anymore. I should have downloaded it, I guess.

So many of the videos and reports become unavailable so quickly. I find some links referenced to NHK news both English and Japanese don't work after a short time. They doesn't seem to do much archiving.

Was footage of the probe traveling through the high dose range published? I have seen video of the camera entering the X-6 penetration and of it exiting into the pedestal but not the travel through the tube where it encounters the 650Sv/h level of distortion.
 

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