Fukushima Japan Earthquake: nuclear plants Fukushima part 2

[turi]

SFP3 progress page:
https://www7.tepco.co.jp/responsibility/decommissioning/action/spent_fuel/unit3-e.html

 

[etudiant]

Very impressive performance by TEPCO. They are eating the elephant, one spoonful at a time, as laid out in their longer term plans..
Presumably a similar approach will be implemented later on units 1 and 2. Once that is done, the actual site fuel removal and cleanup can begin.

 

[Astronuc]

I posted about some open-access reports in the thread on Fukushima discussions.
https://www.physicsforums.com/threa...ear-disaster-discussions.501974/#post-6165013
However, there are two important technical books on the accident progression and report by AESJ. They are not open-access, but must be purchased, but are probably worth the money for serious technical analysis.

A Study of the Fukushima Daiichi Nuclear Accident Process
https://www.springer.com/us/book/9784431555421 e-book $89.00

The Fukushima Daiichi Nuclear Accident
Final Report of the AESJ Investigation Committee
https://www.springer.com/us/book/9784431551591 e-book $129.00

 

[LabratSR]

NHK Documentry - Decommissioning Fukushima Daiichi: Tackling Nuclear Fuel Debris

 

[turi]

Mainichi reports that reactor fuel removal work should start at unit 2 as it seems to be the easiest target: https://mainichi.jp/english/articles/20190809/p2a/00m/0na/005000c
Demolition work on the exhaust stack between units 1 and 2 has started:
https://mainichi.jp/english/articles/20190802/p2a/00m/0na/009000c

 

[LabratSR]

2019.10.31 The method for removing fuel from the Fukushima Daiichi Nuclear Power Station Unit 2 spent fuel pool

https://www4.tepco.co.jp/en/news/li...7LGmvM_5l8fBovBFGpGwMdruH6nq8RIILFmeEbhlXDHjs

 

[LabratSR]

A trip to the Fukushima No. 1 nuclear plant: Full-body suits and three layers of socks

https://www.japantimes.co.jp/news/2...tyRt0hfnU5RiquN9PBm7Tg6f4e6Xv20c#.Xk9B9UBFxHX

 

[LabratSR]

" Exceedingly high radiation levels found inside crippled reactor buildings at the Fukushima No. 1 nuclear plant were labeled by nuclear regulators as an “extremely serious” challenge to the shutdown process and overall decommissioning of the site."

Radiation levels at Fukushima plant far worse than was thought : The Asahi Shimbun

 

[gmax137]

Fukushima Daiichi 3 fuel removal completed : Waste & Recycling - World Nuclear News

Fukushima Daiichi 3 fuel removal completed
01 March 2021The process of removing all 566 fuel assemblies from the storage pool of unit 3 at the damaged Fukushima Daiichi nuclear power plant in Japan was completed yesterday, Tokyo Electric Power Company (Tepco) has announced. Fuel assemblies have already been removed from the pool at unit 4, but such work has yet to start at units 1 and 2.

https://www.world-nuclear-news.org/Articles/Fuel-removal-completed-at-Fukushima-Daiichi-3

 

[Sotan]

Hello again everyone.
Approaching 10 years since the accident there seems to be an increased interest in the situation of Fukushima Daiichi.
I am posting below the link to an article, originally in Japanese, translated with google - I think google translation from Japanese to English has improved considerably in recent times (I wonder if you agree). The article gives some opinions of experts regarding the (im)possibility of removing the fuel debris.
https://translate.google.com/translate?sl=ja&tl=en&u=https://news.infoseek.co.jp/topics/toyokeizai_20210308_414695/?l-id%3DTopMainTopic_busi-econ_1

 

[Charles Smalls]

Hello again everyone.
Approaching 10 years since the accident there seems to be an increased interest in the situation of Fukushima Daiichi.
I am posting below the link to an article, originally in Japanese, translated with google - I think google translation from Japanese to English has improved considerably in recent times (I wonder if you agree). The article gives some opinions of experts regarding the (im)possibility of removing the fuel debris.
https://translate.google.com/translate?sl=ja&tl=en&u=https://news.infoseek.co.jp/topics/toyokeizai_20210308_414695/?l-id%3DTopMainTopic_busi-econ_1

Good article and translation
Hard to believe it’s been an entire decade. Tepco recently posted a 53 minute long slide presentation on their website. It’s all in Japanese but from the images seems to chart their evolving picture of the melt out progression from the 3 cores and where data suggests the bulk of the exited fuel now lies in each unit: https://www4.tepco.co.jp/library/movie/detail-j.html?catid=107299&video_uuid=m88yqm90

Right before the end at 52:45 is the clearest display of the developing estimates for fuel pile locations. Notably all three updates still fall short of modelling fuel melt exit beyond the pedestal area and progress from there i.e. to beneath the suppression pool etc.

A comment on reddit by someone apparently working on the fuel sample/retrieval robot arm linked this video which shows progress on the arms construction: Will be interesting to see the scope of its ambitions

Hope everyone’s safe, see you next big news day or next year

 

[Sotan]

Another year has passed, but I am still following this subject - and maybe others do too.

- A few days ago they sent another underwater robot in the pedestal area of Reactor 1. You can see a video below. Apart from the lumps of "deposit" which are believed to be nuclear fuel debris, this time the images also show barren steel bars which originally were used to reinforce the concrete. It is speculated that the high temperature molten fuel that fell to the bottom of the reactor caused some of the surrounding concrete to "melt". (Does concrete "melt" ? Does it melt in such a way that the reinforcing steel bars remain? Rather then melting perhaps it is some different sort of chemical reaction that erodes it?) Now they worry that some of the molten fuels might not be located in the limited area right under the reaction vessel, but also spread to a certain degree in the surrounding areas too.

Youtube video

*Also a longer video with images from more robot cameras

 

[Rive]

(Does concrete "melt" ? Does it melt in such a way that the reinforcing steel bars remain? Rather then melting perhaps it is some different sort of chemical reaction that erodes it?)

Concrete can melt, but not this way, and when it really melts, the rebars going with it.
This one looks more like some extreme spalling.
The 'concrete' part loses integrity at few hundred degrees and dislocates from the (still solid at that temperature) rebars.
ref
ref2

 

[Astronuc]

some of the surrounding concrete to "melt". (Does concrete "melt" ? Does it melt in such a way that the reinforcing steel bars remain? Rather then melting perhaps it is some different sort of chemical reaction that erodes it?)

Concrete could melt: "The melting point of quartz sand is about 1,650 degrees Celsius while the melting point of cement is approximately 1,550 degrees Celsius."
Ref: https://bagofconcrete.com/what-is-the-melting-point-of-concrete/

The ceramic part of the fuel, UO₂, has a melting temperature of ~2800°C, but some fission products will melt at lower temperatures, or chemically react with water and other materials. The Zircaloy-2 cladding would have a melting temperature about 1850°C, but it would oxidize at much lower temperatures, which would be the reaction that produced hydrogen (Zr + 2 H₂O +> ZrO₂ + 2 H₂). The 'molten' fuel would have also reacted with cooling water, to higher order oxides and chlorides/bromides if seawater.

Stainless steel, or steels in general, melt at about 1375 to 1450°C depending on various factors such as composition, so steel rebar would melting before concrete.

Both carbon steel and stainless steel, and concrete, which is porous, would react chemically with seawater. One can go to a seashore and find examples of corroded steel and degraded concrete, although there are now special concretes and steels that resist corrosion from seawater.

 

[artis]

The 'concrete' part loses integrity at few hundred degrees and dislocates from the (still solid at that temperature) rebars.

I did see your references and I'm not disputing them, but overall I find this to be bit weird. Ordinary house fires with modern plastic and wood furniture etc items easily reach "few hundred degrees" and more at ceiling level.
One of the most common types of residential building around where I live is the 9 story reinforced concrete panel block apartments as well as monolithic concrete pour 16 and higher story buildings.
There is a flat fire regularly in one of them that goes on for an hour or more where red hot flames gush outside the windows. Yet I haven't seen any of those buildings be rendered structurally unsafe after such fire.
The ceiling is typically a reinforced prefabricated concrete panel and after such fires they are just cleaned and their use continues.
The place where I saw something resembling concrete cracking and falling off of the precast slabs was at Grenfell tower in the few videos that are online, but that tower burned for half a day and very thoroughly and yet not even to compromise the structural integrity to the point of collapse, as the tower is still standing.

So I myself am not that certain about exactly how much integrity different concrete mixes and implementations lose within an average few hundred degree fire.
Sadly I cannot find any relevant studies at the moment of the integrity if precast panels under fire for example.

 

[Rive]

Ordinary house fires with modern plastic and wood furniture etc items easily reach "few hundred degrees" and more at ceiling level.

Usually that kind of fire won't heat up the whole concrete panel to that temperature. In such cases only surface spalling (few cm depth) is expected.

I found https://www.researchgate.net/publication/261436338_Fire_Spalling_of_Concrete_Theoretical_and_Experimental_Studies/download some time ago. At the level we need here I think the examples and descriptions alone will do.

 

[Charles Smalls]

It is speculated that the high temperature molten fuel that fell to the bottom of the reactor caused some of the surrounding concrete to "melt".[...] Now they worry that some of the molten fuels might not be located in the limited area right under the reaction vessel, but also spread to a certain degree in the surrounding areas too.

I talked about it back in 2017, the process is called spalling. Great visual demonstration of it here:



and in depth explanation here. Basically extreme heat causes moisture and air pocket pores trapped inside the concrete to expand into steam which explodes the surface concrete off. Varying constituents in the concrete mix also expand from different rates which cause further degrading of the material. The presence moisture accelerates the process by facilitating the migration of water deeper into the concrete where it then rapidly expands as steam. This cycle then repeats.

The spalling process combined with potential damage from the initial earthquake are the most likely culprits behind the compromise in containment that have been causing the persistent ground water contamination problems.

P.S. Would be very helpful if we had a map of the rover location during that video. At certain parts the amount of visual artifacts and grain caused by radiation is off the charts

 

[Sotan]

(not sure how to quote only part of the post above)

P.S. Would be very helpful if we had a map of the rover location during that video. At certain parts the amount of visual artifacts and grain caused by radiation is off the charts

Maybe this information will help a little:

- There are some still camera shots on this page . They might help figure out how things look in various areas. The descriptions and photos can be identified easily based on time stamps:

Pedestal opening, bottom, left side (21:19:25) / Pedestal opening, bottom, right side (21:19:37)
Pedestal opening, bottom, right side, area above the deposit (22:04:54) / Pedestal opening, left side, are above and below the deposit (22:04:57)
Pedestal opening, bottom, right side, area under the deposit / Pedestal opening, inside, in front, looking down (22:10:37)
Pedestal opening, inside, in front (1) (21:21:47) / Pedestal opening, inside, in front (1) (21:20:24)
Jet deflector D, looking down (11:43:50) / Jet deflector C, looking down (15:50:47)
Jet deflector D, back side (13:48:22)

- If you play this movie from the same page linked above, you have these explanation at the bottom at these times (there are 4 cameras, of which the main one, looking forward ("front") is the one providing the image at bottom right. The others are labeled "side/under" - this is the one at top left; "front (in air)", top right; and "rear" (bottom left).
00:21 Jet deflector F, looking down (or: seen from above)
00:28 Jet deflector E, looking down
00:40 Deposit on the floor of the containment vessel
00:56 Vicinity of the "machinery drain sump pump" (? installed in the dry well?)
01:06 Pedestal basis/bottom/foundation area
01:28 Front side of jet deflector E
01:41 Back side of jet deflector E
01:50 Reactor recirculation system (A) pipes
01:57 In front of the opening of the pedestal
02:07 Pedestal basis/bottom/foundation area
02:19 Jet deflector E area
02:34 Jet deflector D, looking down
02:45 Back side of jet deflector D
02:56 Jet deflector C, looking down
03:07 Pedestal basis/bottom/foundation area
03:17 Area inside pedestal, at front, (probably) seen through the opening
03:34 Pedestal opening, basis/bottom/foundation area
03:46 Pedestal opening, basis/bottom/foundation area and inside/at the front

- I may have not used the correct terms every time. I don't know what the jet deflectors are.
- Looking at the screen, sometimes the cameras seem to witness different amounts of radiation artefacts. Maybe they are different cameras or maybe the direction they are pointing at matters.

- On the same page linked at the top of this message there is also a link to this document. Below is a translation of the summary (google translate and a little checking). There is more information in the document, I don't have time right now to translate it all, but if anyone is interesting in something in there, let me know. It explains in more detail and using a map the location of various photos. The "Pedestal opening" which is examined in detail is depicted on the maps by a red line square and the red letters "ペデスタル開口部".

Fukushima Daiichi Power Station Unit 1 Containment vessel internal survey Completion of detailed visual survey of the outer periphery of the pedestal by ROV-A2
<Reference Material>
 A PCV internal survey was conducted with the aim of examining the recovery process and equipment for recovery of deposits in the containment vessel (hereinafter referred to as PCV).
 In the survey, a remote-controlled robot (hereinafter referred to as “water ROV”) developed for this purpose was used to carry out “detailed visual survey inside and outside the pedestal * 1” and “sediment thickness measurement” in sequence. We are planning to get information such as quantity and origin of the sediment.
 Prior to these surveys, ROV-A installed a "guide ring * 2" inside the PCV from August 8 to October.
 The “Detailed visual survey of the outer periphery of the pedestal” using the ROV-A2 was conducted from March 14th, and resumed from May 17th after a temporary suspension of the survey. On May 17th and 18th, we checked the condition of existing structures and the spread of sediments near the pedestal foundation and near the jet deflector * 3 (E) (slide 3 frame).
 On May 19th, near the pedestal opening and near the jet deflectors (C, D) (slide 3 green frame), the state of existing structures and sediments was investigated. We confirmed the spread situation. (Refer to slides 4 to 7 for details.)
 On May 20, 21st, neutral bundle measurement was performed near the pedestal opening and near the jet deflector (E, F, H) (slide 3 small frame). We are currently conducting analysis and evaluation of the obtained data, and will inform you of the results of neutral bundle measurement after the analysis and evaluation are completed.
 The lifting of ROV-A2 during the day started from 11:00 am on May 23, and was completed at 3:23 pm. This completes a detailed visual survey of the outer periphery of the pedestal. After the resumption of the survey on May 17, no significant change in the PCV position and water turbidity was confirmed, and there was no impact on the survey. In addition, no defects were found in the camera image mounted on the ROVA2 during the water.
 We will evaluate the situation confirmed in the detailed visual survey in the future, and if necessary, we will carry out the survey in the mid-season ROV-A2, B, C, D, E scheduled to be carried out in the future. In addition, the results obtained by neutral bundle measurement will be utilized in the future to narrow down the survey range of "sediment debris detection (nuclide analysis / neutral bundle measurement)" by ROV-D.  In the investigation, the work was carried out after constructing a boundary * 4 so that the gas in the PCV would not leak to the outside, and no significant change was confirmed in the data of the monitoring post and dust monitor, and the plant parameters. No radiation effects on the surrounding environment have occurred. We will continue to carefully investigate, safety as our top priority.

 

[Sotan]

Asahi Shimbun article of May 28
"Photos taken by a remote-controlled robotic device sent into the No. 1 reactor found that a large portion of the concrete base supporting the pressure vessel appears to have melted, leaving only a metal framework holding up the pressure vessel.

Experts are now saying the remaining structure may not be strong enough to withstand a big earthquake, a troubling prediction given that the region has been hit by a number of strong temblors in recent months."

 

[Charles Smalls]

Hey all, I was going over some old posts today and was saddened to realize that Jim Hardy had passed away. I remember him being popular here and I'm sure he'll be much missed.

My initial reason for going back was to recall exactly where things had left off and what the main unanswered questions were. With everything back in focus, I must say I find the latest results slightly disturbing. Back in 2017 NHK aired a fantastic investigation into the 3 units which @Sotan posted. Sadly no longer viewable on youtube but we have most of the more useful images still saved here in post #1409. Among the things they theorised, one was possible rapid melt out of fuel from RPVs via the bottom head drainline. Resident BWR expert @Hiddencamper actually made quiet mention of this potential weak point prior in post #1373. This gave a plausible method for rapid core-exit focused into one area without CRD damage, and suggested the type of spalling we should see.

you can clearly make out the textbook morphology of heat induced damage where the material breaks up in a characteristic layered sheet-like manner. But it's just an example. The real spall site of interest is directly outside the Unit 1 pedestal doorway to the PVC. This is the presumed pathway any molten fuel would have flowed along as it left the RV and the latest data shows that the deposited material found there is too inactive to be the fuel itself. That indicates that the fuel did pass through or under that area.

5 years later we finally see visual confirmation of the very heavy spalling we suspected.

Also back in 2017, TEPCO released a very interesting sequence of videos filmed in Unit 5. (right-hand links still work). There's something eerie about the sequence as they basically seem to be charting the exact pathway the fuel would have taken after escaping the the RPV in the sister units. From the CRD room above, through the grating to the pedestal floor and then out the doorway into the PVC proper. This is exactly what the latest 23/05/2022 footage covers and it definitely helps to compare the "before" and "after". One question very rarely raised, is where escaped fuel proceeds from here. Especially given it's super-heated molten state, the spalling, and the channeling effect of the pedestal opening. So let's talk about Jet Deflectors (JD). The PVC drywell (DW) is connected to the tours wetwell (WW) by 8 large vent pipes. These pipes are capped by open vented covers on the DW end called jet deflectors, and permit the movement of air between the DW and WW to prevent damage from potential pressure differentials between the two vessels.

In TEPCOs pdf they are coloured yellow and labeled A-H.

And there's a photograph of one in normal condition in the background here labeled X-5A
Back to the 2017 NHK documentary:

(34:03) According to this graphic, they suspect hot molten fuel somehow made it's way into the suppression pool and burned through the bottom of the torus to contaminate and leak water from there.

(34:09) They seem to be experimenting with different concrete consistencies and mixtures so they can get a mix to pipe into the suppression and plug the suspected leaks.

There was speculation on the thread in 2017 on exactly what this image showed. Clearly a suspected problematic leak in the torus they hoped to plug, but the bright orange colour they used to depict it was unclear. It may have been representing fuel, but at the time we concluded it was simply using a 'hot' colour by coincidence to highlight a suspected leak. If we go to TEPCOs new 23/05/2022 ROV video, we see a lot which may actually be relevant to this. Ignoring the severe pedestal spall damage for a moment, look bottom right at 2:12 and 2:20. Distinct layers where a 'crust' has formed above a material no longer present, leaving a void. The material has since headed off toward the JDs and left this curious gap or hollow space behind. It looks for all the world like a https://caves.org/virtual/virtual_tube/birth1.jpg, where molten material has passed on, leaving a thin crust of material 'floating' above.

Impressively, the ROV follows these crusts and material build-ups which have pilled up against the JDs, even going so far as to enter JD-D to film the other side (2:46). The high amount of noise and sparkle indicates the presence of high radioactivity, but more tellingly, notice that in JD-C, D and E, the video is edited to cut just before the camera pans round to film vent pipe and pathway down to the WW (2:54). In an earlier ROV mission, we see the full pan around of JD-G, but none in these three. As JD-C,D and E are pretty much directly opposite the pedestal opening, I speculate that the molten fuel would have flowed and spalled its way straight into these vents, causing a large amount of severe damage down to the WW which TEPCO don't wish to publicly disclose at this point. It's also possible the experts who consulted with NHK to produce that 2017 special suspected this all along (wish it was still available). That would align well with those graphics. What all this means as far as the 7m thick basemat, with the fuel likely taking a shortcut around it to down under the WW, and whether this is also the case in the other 2 units is still unknown. Probably not in unit 3 as the it still holds water quite well, but very likely in unit 2. It's difficult to build a complete picture as TEPCO is still being selective with the images it discloses, but I think this confirms the most likely route for possible ground penetration leading to the persistent ground water contamination issues they've been battling. Difficult to see how best they recover fuel that's gone as far as to leave the containment entirely. Hopefully we get a similar ROV investigation of Unit 3 soon, and some numbers of this one to estimate likely presence of local fuel to see exactly how much went where.

Take care all,
Rip old Jim

 

[Sotan]

RIP Jim Hardy...

Thank you Charles Small for your post. I cannot say anything of substance about the possibility of molten fuel going through the big pipes into the S/C. Animations at the time (see the 2018 version of that video below) tend to depict the molten fuel at the bottom of the pedestal but somehow not rising high enough to reach the jet deflectors. We know now from rover images that it did rise, deposits are shown engulfing the jet deflectors at least in part (and there is a scene somewhere in which someone estimates the thickness of the deposit at ~60cm, so it depends how high those jet deflectors are situated, above the floor). With the violence of the phenomena going on in the pedestal area at the time it is not impossible to imagine chunks/splashes of stuff going in all directions available. (Let me also mention here this article of Nov 2021 - Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior - which may be of interested to some.)

- So indeed the 2017 movie you mentioned is gone private but it seems NHK keeps refreshing that with new information every year. there should be a 2021 version but it seems to be pay per view, only on NHK site. I was able to find the 2018 version of that video, which has interesting images and information, too. It is in Japanese but closed captions help, to a degree.
At 6:50 they imagine the fuel melting process, the molten stuff goes at the bottom and stays put. Doesn't rise too far up...
8:47: the handle of a fuel bundle seen in the solidified deposit
9:20 estimation of the thickness/height of the deposit, about knee-high
16:16 and after - images from Reactor 5, which is similar to Reactor 2 which was depicted until now. Workers go under the RPV, we see the control rods.
A lot of discussion, experts and workers' opinions, including comparison with Three Miles Island (where things were nowhere as difficult), and realization of the difficulties of the task of decommissioning.

- A similar video but more recent (Feb. 21 but includes images from 2018 too) is here. Again at 5:56 they go under the PCV of Unit 5, then go lower into the pedestal and at 7:50 talk about the thickness/height of the solidified deposit in Unit 2, estimating it at about 60 cm. *My thoughts seeing this: Is it high enough to support the idea of molten fuel going through the big pipes into the torus? Is it a case of slow and quiet rising up of a liquid mass, like water in a sink when the faucet is left open and the bottom hole blocked, and then starts pouring out through these pipes - or is it rather a violent phenomenon in which everything flies everywhere and in that case we don't have to think too much about heights and levels...

 

[Astronuc]

"Photos taken by a remote-controlled robotic device sent into the No. 1 reactor found that a large portion of the concrete base supporting the pressure vessel appears to have melted, leaving only a metal framework holding up the pressure vessel.

That's a puzzling statement given that the steel would melt at a lower temperature than concrete, i.e., if the concrete had melted, the steel should have melted before the concrete. Perhaps the concrete reacted chemically with seawater and whatever compounds were in the seawater.

 

[Sotan]

That expression - and those extraordinary images - puzzled me too, hence why I posted "does concrete melt in such a way that steel bars remain?". And was wondering of some chemical reaction too.

But now I think it's rather a matter of "lost in translation". In an interview one worker says "it melted... or evaporated" (!). So I think what they intend to convey is more like "that concrete... disappeared". It's not there anymore. They don't really explain how it happened, just describe the result.

This still leaves the question what happened exactly. But salt water, and I'm only talking intuitively, appears too benign to me to be able to cause such huge results (maybe I'm wrong). I am inclined to give credit to the spalling explanation that has been suggested. It's just that the spalling video and articles seem to speak of a more superficial or partial erosions of concrete, and again intuition tends to say what we see here is different. But maybe higher temperature, long contact time and the contact with a molten mass of metal (rather than hot air from a fire) over a long time kept the spalling process going...
Still - how the concrete got cleaned so nicely away from the steel, I mean it's eery. So temperature did not exceed melting point of steel. How thick was that wall. Is the concrete gone everywhere, 360 degrees? Or just in portions? Is the whole thing now really supported by those steel bars only? High temperatures would not have weakened that steel dangerously?

I suppose that is why they plan to continue investigations for the next 6 months.

 

[Sotan]

March 23 Report on measurements of the thickness of the deposit at the bottom of Unit 1 PCV
(The report is in Japanese. Page 3 contains most of the information.)
They used a version of the robot that floats on the surface of the PCV water and sends ultrasounds towards the deposit and analyzes the reflection. They thus estimated at 1.0 ~ 1.2m the distance from the water surface to the deposit surface; knowing that water surface is at 2m from the bottom of the PCV, the thickness of the deposit has been evaluated at 0.8 ~ 1.0m.
This robot cannot give detailed information about the structure of the deposit, but results indicate that at the top there is a layer of a couple/few centimeters of finer particles (like a powder or mud layer) and then a more solid deposit (pebble/rock type). Another robot will follow investigating that in more detail, and then another will try to get a sample.

 

[Rive]

Is the whole thing now really supported by those steel bars only? High temperatures would not have weakened that steel dangerously?

Rebars does not supposed to have (significant) structural strength without the support of concrete. High temperatures are just extra.
However: right now the mass of the supported structure has decreased by a lot (all fuel, water and most of the internal structure left the PCV...) so I hope/think it'll be temporarily OK with hanging on the connected pipes and with reduced support.

 

[Charles Smalls]

How the concrete got cleaned so nicely away from the steel? Temperature did not exceed melting point of steel. How thick was that wall? Is the concrete gone everywhere, 360 degrees? Or just in portions? Is the whole thing now really supported by those steel bars only?

According to areas marked red in this TEPCO pdf, they seem to be estimating severe concrete damage to ~27% of the pedestal concentrated around the doorway. Plus the pedestal inner walls.

The pdf source says 2016 though, so it's possible that further damage has been observed in later investigations. Prior to any damage, the pedestal wall was approximately ~0.65m thick. That number comes from a 1989 paper on "Liner Failure Potential in MARK-1", which looks specifically at fuel attacking concrete and melting through the outer containment. The reactor they base their study on is almost identical to Fukushima unit 1.

Couple of interesting things:

These values do not account for the sensible heat needed to raise the concrete components from the decomposition temperature to the melt temperature [...] Of particular significance is the high melting temperature of the limestone concrete, which is higher than the melting temperature of steel

So there's a range of temperatures at play here: one where concrete undergoes decomposition or ablation (what I called spalling), a higher one where steel will melt and a higher one yet where the concrete itself becomes liquid. (depending on concrete type). This is one possible explanation for why unit 1 can have such dramatically damaged concrete while still leaving the steel rebar unmelted.

The gases rising from the decomposed concrete( H20 and C02 ) cam react with the zirconium metal present, leading to a heat source that can overshadow the decay heat [of the molten fuel].

So depending on the mix and composition of the meltout, the zircalloy cladding within it can actually accelerate the decomposition once it contacts the concrete. So that's a nice little positive feedback loop there.> [Our] spreading analysis ignores the possible presence of water in and out of the pedestal. Such a dry case is expected to pose a much higher threat to the liner than the wet case, due to the considerable potential for melt quench and cooldown via thermal interaction with the water pool.

This lines up well with the images from @Sotan's news investigations.

I haven't seen the underlying data, but all the event reconstructions I'm aware of all specifically depict unit 3 as having water in the containment prior to fuel melt out. This makes sense when we look at the three units today with unit 3 holding water best, while units 1 and 2 struggle, suggesting possible containment penetration via fuel melt. Difficult to say with TEPCO's highly selective data release. I know I mentioned this before but I think it warrants restating:

In the first investigation video at 2:41 the ROV enters jet deflector H furthest from the pedestal doorway, and we see a nice clear view as the camera pans around and shows a relatively clean vent tube.

Later in part two, at 1:43 the ROV enters jet deflector E directly opposite the doorway. The timestamp is 14:17 and the camera just begins to glimpse what look like fuel deposits. Scandalously the video cuts, picking up again fully 3 hours at 17:05. At 2:44 of the same video, the ROV next enters jet deflector D. Timestamp is 13:43 and there is a high amount of radiation noise and sparkle. The camera pans around barely 1/4 of the way showing some material intrusion, before abruptly cutting off and picking back up again outside the deflector with the timestamp 15:50. Incredible.

I'm sure we'll get more interesting releases from TEPCO in the future but whether they can be taken at face value or require extra work to interpret is another matter. Some things however, like the danger of that pedestal and it's earthquake fragility can't be obscured.

 

[Sotan]

Some information from this document dated 27 Oct 2022. (Page numbers indicated below are as given in the top left corner by Adobe Reader for whole PDF file (total 57 pages). There are other page numbers too, for each section, and this can cause some confusion.)

P4: They are planning to sample the water contained in the S/C chamber of Unit1 PCV. P5: One of the means to improve quake resistance of Unit 1 PCV is lowering the level of water in the PCV. They are therefore working on installing the necessary pipes, while making use of existing pipes too (like CUW – reactor water cleanup system?). Note 1* The needed pipes for removing such water in Unit 3 – making use of existing RHR, residual heat remover, pipes too – are already installed. As a first step they need to check the properties of the water in the S/C, and for this they plan an inspection/sampling operation, which has started these days and should end in Jan next year. There are some diagrams and a photo explaining the concerned are: first floor of Unit 1 reactor building with candidate spot for inserting new pipes (1-10mSv/h area); existing pipes; non-return valve on the CUW pipe. P11: Process planned for lowering the level of water in the PCV of Unit 1. The approximate goal, for now, is to bring water level around the “center” of the S/C pipes.P12~33 show the work being done in preparation for new inspections and, later on, sampling of debris from Unit 2 RPV. There is a lot of site preparation, robot testing and improving, and personnel training going on.P34~ : New data presented by IRID / JAEA regarding the characterization of the fuel debris situation inside the damaged RPVs. As they keep gathering information, they work on improving the degree of understanding regarding what exactly is in there.

P36: refers to Unit 2. The new findings are at the bottom of the page. – As the fuel debris accumulated at the bottom of the RPV, a new rise in temperature greatly affected the course of the accident; the fuel debris containing a lot of metal melted first, at 1000-1300°C, then damaged the RPV wall in places, and then poured onto the pedestal floor. – The fuel debris that leaked/accumulated on the pedestal floor got cooler and did not succeed in “melting” the concrete; therefore, if right after the accident it was assumed that a MCCI (Molten core/Concrete Interaction?) happened, it is (now) assumed that the MCCI was almost absent.

P37: refers to Unit 3. The new findings are at the bottom of the page. – As the fuel debris accumulated at the bottom of the RPV, a new rise in temperature greatly affected the course of the accident; the fuel debris containing a lot of metal melted first, at 1000-1300°C, but then, the fuel debris containing a lot of oxide compounds reached a high viscosity state (like a “hard liquid mixture”? sorry can’t find a good word), at 2000-2300°C, which damaged the RPV bottom on a rather large area and, over a few hours, fell on the pedestal floor. – The debris thus accumulated on the pedestal floor, due to its high viscosity, did not closely interact with the concrete; therefore, if right after the accident it was assumed that a MCCI (Molten core/Concrete Interaction?) happened, it is (now) assumed that the MCCI was almost absent.

P38: new insights on the state of the fuel debris. They speak about results of analysis of some small grains/particle harvested in some previous investigation, results which are now added into a “debrisWiki” database. I think it is accessible here https://fdada-plus.info/wiki/index.php, English version here: https://fdada--plus-info.translate...._sl=ja&_x_tr_tl=en&_x_tr_hl=ja&_x_tr_pto=wapp

P43~ : Report on the second part of the investigation into Unit 1 PCV. Interesting new images on P48-50, including a weird ball-shaped piece of debris found on the floor of the pedestal. Looks like a solidified bubble with holes in it.

 

[SteveElbows]

Thanks for that update. The DebrisWiki site is useful. They also review their understanding of core damage and accident progression on that site. As we already know from past stuff such as the missing concrete in unit 1, there is an assumption of plenty of MCCI there. And just like in the report you mention, they now think that MCCI didnt happen much in reactor 2. When it comes to reactor 3, I think perhaps they are still hedging their bets a bit. eg this is the translation from DebrisWiki In these respects:

Unit 1:

It is highly likely that almost all of the fuel debris migrated to the pedestal, spread over the pedestal floor, caused Link Removed , and eroded the concrete.

The causes of hydrogen generation include the cooling water-Zr reaction and MCCI in the core, but it is highly likely that most of the hydrogen generated by the former has already been discharged from the reactor building. The following two routes are conceivable as hydrogen release routes.

• Hydrogen generated in the core → safety relief valve (SRV) → S/C → D/W → PCV top flange → reactor building
• Hydrogen generated in MCCI→D/W→PCV top flange→Reactor building

After the high-temperature fuel debris migrated to the pedestal, it is possible that sufficient cooling water was not injected into the pedestal for about 10 days. Therefore, the pedestal is filled with high-temperature steam (approximately 400°C according to the rough analysis using the STAR-CCM+ code [1] ), and the inner wall of the pedestal is heated by radiation (the rough analysis using the STAR-CCM+ code [1] ] estimated that the temperature was approximately 800°C), and some of the concrete and other structural materials may have been damaged at this stage.

Unit 2:

It is highly likely that the transition from the lower plenum to the pedestal consisted mainly of molten metal or a relatively low melting point such as U-Zr-O. Such migration of core material to the pedestal occurred within a period of several hours, and it is possible that most of the oxide-based debris remained inside the RPV. At the lower end of the CRD near the application in the RPV, deposits thought to be debris were found, and it is possible that a small amount of debris was released through this part. The gratings of the platform directly below this position and the intermediate frame below it have fallen off, but the grating of the adjacent part of the intermediate frame (the grating of the platform directly above remains) has also fallen off. In addition, considering the condition of the deposits remaining on the grating that remained on the platform, it is presumed that the spilled debris was a highly viscous fluid with a temperature below the melting point of steel. Since the temperature of outflow debris was not so high and the amount of outflow was small, it is considered that MCCI hardly occurred.

Unit 3:

Since the D/W pressure began to rise from around 0:00 on March 14, it is believed that the core material that had migrated to the pedestal at this point was evaporating the cooling water that had been in the pedestal. However, since the D/W pressure rise was slow, it is highly possible that the migration of core materials to the pedestal was extremely slow. After 0:00 on March 14, the D/W pressure gradually increased until around 7:00 on the same day. This pressure increase is thought to correspond to the steam generation at the pedestal, and it took about 7 hours. It is presumed that pedestal migration of debris has occurred on the scale.

Investigations inside the pedestal confirmed deposits of 2 to 3 m, but this volume cannot be explained by the fact that the core materials are densely packed, and there are considerable gaps inside the deposits. There is a possibility that If a significant MCCI had occurred, the debris would have reached a considerably high temperature, which is incompatible with having many gaps in the sediments. Based on this, it has been pointed out that MCCI may not occur very often in Unit 3. On the other hand, it is possible that remelting occurred inside the pedestal sediment, and in that case, the phase state is expected to become complicated due to component segregation, remelting, and resolidification. Again, the solidification rate is likely to affect the properties of fuel debris.

I got those quotes from the three pages that are linked to from this page about accident progression:

https://fdada--plus-info.translate.goog/wiki/index.php?title=事故進展の推定&_x_tr_sl=ja&_x_tr_tl=en&_x_tr_hl=ja&_x_tr_pto=wapp

The visual diagrams on those pages, which are mostly the same as the ones in the report you mention, also imply they might be hedging their bets in regards unit 3 MCCI, since there is still some colouring down in the pedestal floor concrete area of that reactor.

Those summaries are quite useful in other ways. It had been years since I last looked at this sort of detail. So it was useful to see them putting the timeline of observed reactor and D/W pressures into a short narrative about the meltdowns that was not trying to obfuscate the seriousness of the incidents and extent of fuel melt like some of the early 2011 analysis did. They even mention the neutron detection episodes in an attempt to make educated guesses about timing of various stages of fuel damage and debris slumping at reactors 2 and 3.

 

[SteveElbows]

By the way, after quite a number of years of not paying as much attention as I did in the first years after the disaster, I found it rather tedious trying to search for the English versions of TEPCO documents that come out these days, due to changes in how their website is organised. Sometimes I was still finding the documents via links they put on the photos page that still work, but these tended to be initial reports of that days work and the photos and video the work yielded, rather than final analysis. I know that many of these investigations tend to be reported here in this thread thanks to the hard work of people here offering translation of the Japanese versions, but sometimes I want to look at English versions later on to help keep everything organised in my mind.

Anyway after much stumbling around today I finally found the page where the interesting English reports are announced and linked to these days (as well as plenty of less interesting ones which I skip over). https://www.tepco.co.jp/en/hd/decommission/information/newsrelease/reference/index-e.html

A couple of my favourites from the last 4 years or so:

Unit 1 internal investigation report from late May 2022:

https://www.tepco.co.jp/en/hd/decom...eference/pdf/2022/reference_20220526_02-e.pdf

The April 2018 Unit 2 investigation document which remains one of the better ones I've ever seen from them, in terms of pedestal area analysis with clear photos and useful explanations of the location and the detail:

https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2018/images/handouts_180426_02-e.pdf

 

[Sotan]

Thank you very much SteveElbows for the two very informative and well written posts. It's been a while so let me say again that due to my lack of time (but more importantly lack of... proper knowledge in the field) my posts are at best approximative. I'm just hoping they can restart the discussion :)

The page you found with English reports is great, it is a little delayed of course but at this point such a delay is probably not a big problem.

More on topic: they seem eager and pleased to state that evidence suggests not much MCCI happened - but how does that match the images with the naked steel bars supporting the RPV?

 

[SteveElbows]

Thanks. I am just a layperson too, who had a very large amount of time to pay attention to this disaster in the first years, and who always enjoyed talking here about it 10+ years ago with knowledgable and inquisitive people. And now its only in recent years that they reached the point of site investigation that renewed my interest, eg some reasonably good quality images of the state of things in the pedestal areas.

In regards their comments about MCCI and how that relates to eroded concrete images, I don't think there is a contradiction. Because the photos showing the exposed rebar are from unit 1, and they do think MCCI happened at that particular reactors base. Its unit 2 where they downplay the possibility of much MCCI, and then with unit 3 they are hedging their bets about the extent to which it might have happened.

 

[Sotan]

The Nuclear Regulatory Authority (NRA) of Japan also has periodic meetings in which experts from various institutions and organizations discuss recent reports coming from Fukushima Daiichi, as well as additional studies and results. Unfortunately they are mostly in Japanese, but exploring the English version can also provide some data.

- The list of NRA meetings dedicated on the analysis of the Fukushima Daiichi accident is on this page. Most recent was on Oct 31. The blue rectangle named 会議資料 leads to the written materials used in that particular meeting. Lower on the page there is a link named 会議映像 which leads to the recording of the meeting on youtube. The recording for the meeting of Oct 31 is here, it is over 4h long, and one of the subjects discussed (among many) is the matter of the missing concrete and exposed rebar. At around 38:19 an associate professor from Osaka University (mr. Oishi) presents a study carried out by his team, discussing this subject. They make some theoretical analysis of the factors that might have led to that state of the bottom of the RPV and in the second part they present some experimental results on concrete and rebar behavior at high temperatures.

I am picking to report this not because there is something extraordinarily new or significant to report but because in their analysis they mention a second factor, besides MCCI, that might have contributed significantly to the disappearance of the concrete. At 42:04 they list the possible factors and two of them (marked with A in the rightmost column) are considered significant, one (B) is so-so, and 4 others (marked with C are considered less likely to have contributed. A-factors are MCCI and "dissolution in water": some components of concrete can get dissolved in water, especially SiO₂. The reaction obviously needs the presence of water and can happen even at temperature as low as 200^oC. (The B-factor is mechanical erosion.)

The chief of NRA at 1:22:19 considers this as significant. The hot molten fuel falling in the water at the bottom of the PCV inevitably raises the water temperature and the creates conditions for the dissolving of the concrete, while leaving the steel bars relatively unaffected - even without actual MCCI taking place. Or at least this possibility too should be taken into consideration and further investigated through actual experiments in the lab.

Of course this is just a very little snippet taken from a 4h meeting. So much to see and read...

 

[Astronuc]

P37: refers to Unit 3. The new findings are at the bottom of the page. – As the fuel debris accumulated at the bottom of the RPV, a new rise in temperature greatly affected the course of the accident; the fuel debris containing a lot of metal melted first, at 1000-1300°C, but then, the fuel debris containing a lot of oxide compounds reached a high viscosity state (like a “hard liquid mixture”? sorry can’t find a good word), at 2000-2300°C, which damaged the RPV bottom on a rather large area and, over a few hours, fell on the pedestal floor.

I think "hard liquid mixture" simple means a very viscous material, perhaps shy of melting, where the material is not quite liquid, but has little strength/stiffness. In other words, in such a state, there is essentially no yield strength and the material flows, rather than creep. That usually a state of matter the mechanical/structural engineers would avoid.

The statement about the "fuel debris containing a lot of metal melted first, at 1000-1300°C," is interesting because I'm not sure what 'metals' or rather alloys, that would be, unless it refers to some lower melting eutectic/eutectoid or mix of such. Type 300 stainless steels (e.g., 304/316) would have melting points about 1370-1400°C (~2500-2550°F), nickel alloys (e.g., X750, Inconel 718) slightly higher, and Zircaloy (1820-1850°C, ~3310-3360°F), and UO₂ melts at ~2840°C (~5070°F); however, corium, a combination of alloy and metal oxides could have a lower melting point depending on types of metals and stoichiometry. Certainly, beyond 1400°C, such a hot mass from the core could melt the steel supporting structure and flow downward throught the pressure vessel (bottom head) and onto the structures underneath, e.g., pedestal. This would suggest that they did not get cooling water into the system.

 

[Sotan]

Hello Astronuc. Let me add a few things to what you said above - mainly just to keep the topic going and because I had some time to browse more.

- About the lack of cooling water in the system, indeed there seem to be plenty of such mentions in the "Accident progression at Unit 3" which you can reach by visiting the DebrisWiki site linked by SteveElbows in his post of Nov 10 above - or via this link which gives it in google translation. "Water injection by HPCI stopped...boiled lower plenum water rapidly supplied steam to the core... depletion of liquid water in the lower plenum... which caused a rise in the temperature of the debris in the lower plenum... the RPV boundary was damaged and the debris flowed toward the pedestal... evaporating the cooling water that had been in the pedestal." (I highlighted just the phrases referring to the cooling water.)

- The above "Accident progression at Unit 3" text does not seem to clarify much my poor translation about "metals" melting. So I went back to Page 37 of that PDF to try and improve my translation. There was just one more mention that I overlooked: "Oxidized debris: from all the fuel debris (this refers mainly to) uranium, zirconium and stainless steel components in an oxidized state". As for my translation I cannot improve it much after all, but if I were to, it would be: "- As the fuel debris accumulated at the bottom of the RPV, a new rise in temperature greatly affected the course of the accident; the (parts of) fuel debris containing a lot of metal components melted first, at 1000-1300°C, but then, the (parts of) fuel debris containing a higher proportion of oxide compounds reached a high viscosity state (the literal translation would be “solid-liquid mixture”), at 2000-2300°C, which damaged the RPV bottom on a rather large area and, over a few hours, fell on the pedestal floor." I think what puzzles you a bit is the lower range of temperatures mentioned (1000-1300°C).

I tried to find more information about what type of compounds they suspect melted in that range.　Among the documents shown in NRA meeting mentioned in my previous post there is this PDF which deals with findings of the PCV inspection of Unit 1. Second slide of this PDF (with a big number 37 at the bottom) mentions the amounts of various materials present in the PCV. Amount of fuel debris 279 tons of which 76 tons of fuel component (UO₂...), 73 tons of fuel structural materials (Zr, SUS - I guess SUS refers to stainless steel), 130 tons of concrete. The volume of fuel debris is ~16m³. Then melting points are mentioned: ~2800°C for UO2, ~1850°C for Zr, 1400-1450°C for stainless steel and - only this one seems to be missing from your post - Pb, lead from shielding components, with a melting point of ~330°C. They don't say how much lead might have been in there so maybe not "that" much. Not sure if it matters much with regard to the more damaging processes that took place at higher temperatures.
- Next slide (number 3 or 38, whichever you like) mentions "melting of metallic components from inside the RPV - melting point somewhere around 1200-1300°C."

- Moving on to another subject, in the list of documents from that NRA meeting the documents which contain in their name 4-1, 4-2 and 4-3 talk about the observed significant deformation of the shield plugs. 4-1 reports that older finding that the shield plugs of Unit 1, 2, 3, 5 show a certain degree of deformation. Most recently Unit 6 was investigated and the results are shown in diagrams. The shield of Unit 6, some of its central parts especially, are deformed, as if they got lowered in some areas by about 20mm (page numbered 138-139). Page 140 shows diagrams of the shield plugs of Unit 2 and 5, with a similar phenomenon. Page 141 shows the shield plug in Shimane NPP and Tsuruga Unit 1, which are considered to show no signifivant deformation. Last page in the slide summarizes: Fukushima units 1, 2, 3, 5 show deformation of the shield plus; Fukushima Unit 6, Shimane 1 and Tsuruga 1 shield plugs show no deformation. Perhaps for Fukushima 1 and 3 the deformation can be linked to the hydrogen explosions but for Fukushima 2 and 5 it's unlikely that the deformation was caused by some external force. Possible causes may be: deformation already existing or occurred at construction/installation time; or gradually occurred in time. It may have played a role in creating a route or contributing to the escape of radioactive materials during the accident. This is further explored in documents 4-2 and 4-3.

- Finally - unrelated: a video from the May 2022 inspection of Unit 1 PCV which I only saw now for the first time, maybe someone is interested to see it. The exposed rebars, again... (By the way somewhere in the 4h video of the NRA meeting and in one of the documents they mention that there appears to be a sufficiently large route for then to some day guide one of those underwater robots into the pedestal.)

 

[Astronuc]

https://www.marlinwire.com/blog/what-is-the-melting-point-of-stainless-steelPb, lead from shielding components, with a melting point of ~330°C.

I'm not sure where Pb would be used, even as shielding, inside the RPV.

In stainless steel, typically 300-series, e.g., 304/316, would melting temperatures from about 1375-1400°C for 316, and about 1400-1450°C for 304, depending on carbon and alloying content.

• Grade 304. 1400-1450°C (2552-2642°F)
• Grade 316. 1375-1400°C (2507-2552°F)
• Grade 430. 1425-1510°C (2597-2750°F)
• Grade 434. 1426-1510°C (2600-2750°F)
• Grade 420. 1450-1510°C (2642-2750°F)
• Grade 410. 1480-1530°C (2696-2786°F)

Ref: https://www.marlinwire.com/blog/what-is-the-melting-point-of-stainless-steel
Numbers can be found at BSSA.

Fuel components may be made of a 300 series stainless steel, and Inconel (or Ni-based) alloy (X750, 718 or 625), or Zr alloy (Zircaloy-4, ZIRLO, . . . ). In BWRs, the fuel cladding and water rods are composed of Zircaloy-2, similar to Zircaloy-4, but with a small amount (~0.05 to 0.07 wt%) Ni. The water rods and channels, the latter forming an envelope or shroud around the fuel assembly (designed to direct the water vertically and preclude cross-flow), may be formed of Zircaloy-4, Zircaloy-2, or NSF, which is similar to ZIRLO.

Ref: Zircaloy, https://www.atimaterials.com/Produc...zirconium/alloy/Zr_nuke_waste_disposal_v2.pdf

One does have to be careful of impurities, e.g., S and P, which may form low melting compounds in stainless steels, so those are kept very low, especially for stainless steels to be used withing the core. Stainless steels are typically used in cast, forged or otherwise worked form.

 

[Sotan]

- The WikiDebris site is growing nicely, I think we will use it more and more in the future.
Here is the article regarding "Melting and solidification behavior of fuels and structures during severe accidents" - in Google translation. I think it is more like a general review of the knowledge in the field, not necessarily limited to Fukushima, but very informative.

- Also it's been a while since IRID was mentioned. I found on their site an impressive 60-page PDF in English, recently posted, summarizing their numerous directions of research and development and the progress made in 10 years. You can find it here.

 

[Sotan]

Another nice batch of documents on the Tepco site that could be interesting for the specialists: a list of reports on unconfirmed and unexplained matters in the Fukushima Daiichi Nuclear Power Station accident.
The reports are in Japanese and simply pasting the URL in google translate does not work, but I discovered now that if you save the PDF and then bring the PDF file into google translate's field for translating "Documents", it will provide the English translation. (as always, small translation issues may be present; also might be limited to documents up to 300-pages).

The list contains the following items:
Overview of MAAP Code (617KB)
Topic List (3.05MB)
Latest analysis results by MAAP5 (1.54MB)
Investigation status related to estimation of the state inside the core and containment vessel (25.6MB)
Grasp of accident situation by sample analysis (3.75MB)
About the arrival time of the tsunami that hit the Fukushima Daiichi Nuclear Power Station (9.50MB)
Additional study on loss of emergency AC power due to tsunami (1.82MB)
Regarding setting of water injection amount in Unit 1 MAAP analysis (96.6KB)
Estimation based on the behavior of Unit 1 fuel range water level gauge (259KB)
Impact of the earthquake on Unit 1 (1.02MB)
Study on Reactor Water Injection by Fire Engine (1.01MB)
Study on water injection volume for Unit 1 reactor water injection by fire engines (528KB)
Estimation of accident progress based on Unit 1 measurement data and past analysis results (766KB)
Status of heat removal in Unit 1 isolation condenser (519KB)
Migration Behavior of Molten Fuel to Lower Core (3.63MB)
Estimation of the cause of high-dose contamination of Unit 1 RCW piping (1.19MB)
Analysis of the hydrogen explosion that occurred in the Unit 1 reactor building (2.37MB)
Estimation of accident progress at Unit 1 based on air dose rate monitoring data (1.33MB)
Identification of the cause of the high dose rate observed in the southeast area on the 1st floor of the Unit 1 Reactor Building (2.13MB)
Reactor pressure change in Unit 2 (310KB)
Containment vessel pressure change in Unit 2 (350KB)
Regarding setting of water injection amount in Unit 2 MAAP analysis (146KB)
RCIC flow rate after Unit 2 control power loss (313KB)
Status of the RHR system after the Unit 2 tsunami arrived (751KB)
Containment vessel pressure behavior from around 12:00 on the 14th of Unit 2 (928KB)
Relationship between neutrons observed at the time of the accident and fuel melting (294KB)
Investigation related to the integrity of the suppression chamber (S/C) of Unit 2 (689KB)
Evaluation of reactor pressure rise after forced reactor depressurization in Unit 2 using thermal-hydraulic analysis code (1.23MB)
Rapid increase in CAMS measurement values for Unit 2 on the 15th (153KB)
FP migration behavior estimated from the CAMS measurements taken on the 14th and 15th of Unit 2 (935KB)
Operation of SRV after core damage (932KB)
Changes in water level and temperature in the suppression chamber (S/C) of Unit 2 (1.36MB)
Estimation of reactor water level at the time when core damage/core melt progressed in Unit 2 (0.99MB)
Estimation of the reason why high dose rate was not observed in Unit 2 reactor auxiliary cooling water system (2.14MB)
Decrease in Unit 2 containment vessel pressure in the morning of March 15 (1.66MB)
Regarding the behavior of the S/C pressure gauge after 21:00 on March 14, Unit 2 (1.67MB)
Evaluation method for core damage ratio of Mark-I containment vessel (730KB)
Reactor pressure during operation of the high-pressure water injection system at Unit 3 (206KB)
Regarding setting of water injection amount in Unit 3 MAAP analysis (248KB)
Behavior of reactor pressure drop that occurred around 9:00 on March 13, Unit 3 (1.01MB)
Reactor pressure behavior from 02:00 to 12:00 on March 13, Unit 3 (1.08MB)
About the cause of the outage of Unit 3 RCIC (883KB)
Dose increase around March 20 (1.34MB)
Factors behind the increase in containment vessel pressure at Unit 3 from 3/11 to 3/12 (1.37MB)
Leakage from Unit 3 containment vessel and large amount of steam release (1.03MB)
Estimation of reactor water level behavior during the period when core damage/core melt progressed in Unit 3 (533KB)
Evaluation of the proportion of Unit 3 vent gas that flowed into the Unit 4 reactor building (1.09MB)
Study on Unit 3 suppression chamber water level (1.47MB)
Accident progress after depressurization of Unit 3 reactor (2.31MB)
Investigation of plant status during Unit 3 RCIC operation (1.72MB)

 

[Charles Smalls]

Wonderful footage of Fukushima Unit 1 being constructed in the 1960s. Part one shows the original ocean and soil surveys, laying the sea wall and the bulldozing of the cliffs to bring the site down to sea level (19m05s):

Part 2 has ok auto-translate subs. It shows more cliff demolition, GE handing over the 'turn key', and a shot into the reactor testing one of the emergency core cooling systems (12m39s)

there appears to be a sufficiently large route for then to some day guide one of those underwater robots into the pedestal

Speaking of Unit 1's pedestal and it's rebar, this clip of degraded footage seems to show the original pouring of the unit 1 concrete. It's only a snippet but I think that's it around 6:16

 

[Sotan]

Hello everyone and a Happy New Year to you!

- I had time in this holiday to watch the movies found by Charles Smalls (thank you for those). A little eerie feeling watching the second video around 11:30 where they speak about the safety measures; the plant being built with the assumption that machines do break, people do make mistakes, therefore there are a lot of safety measure incorporated to "1) stop the mishap 2) cool (the reactors) and 3) contain stuff"... The intention is to reassure the viewer regarding the safety of the plant but - in hindsight, of course... - it's obvious that the circumstances of March 11 2011 exceeded what had been planned for.

- There was another NRA meeting on Dec 20 last year, the documents discussed being listed here (in Japanese).
This document in particular summarizes the findings from the first half of Unit 1 PCV investigation by robots which was carried out in 2022. There is a wealth of information in there but what I find impressive is the long list of "types" of debris, classified based on their shape and location. For each type they attempt a certain degree of characterization and speculation. Just an example, because the matter of molten lead debris has been mentioned before: on page numbered "34" they point out that around the PLR pipes there can be seen some peculiar local "rises" in the debris. As we move away from the pedestal opening, the general tendency is for the height of debris to decrease, but contrary to that tendency, here and there they found small "mounds" of debris with a peculiar aspect. A key indication as for their origin is given by a "connector" or "bracelet" part that originally served to tie in place some lead wool blankets. The temperature in the PCV on March 20, 2011 reached and exceeded ~400C (the limit of the thermometer) which is higher than the melting point of lead and therefore they presume those mounds are molten lead blankets. Lead is also mentioned on pages numbered 37 and 38 where "thread-like debris" is described; the lead blankets originally had a fiberglass cover and as the led melt and went away some of it could get attached to those fibers and solidified to create such "thread-like" debris which is seen attached to various structural components in the PCV. Page 39 shows that weird ball-like piece of debris that I mentioned before, and in the "origin" field they wrote, honestly, "unknown". At least at this time. There are many other types of debris - stuff that is stuck to structures, "icicle"-shaped formations, boulders, shelf- or plate- or tabletop-shaped ones. Page 32 shows that a piece of debris was hit by the robot and broke away.
The second half of this investigation has started in December 2022 and will take a few months, until end of March at least.

- Finally I would like to mention this video published a month ago which presents the robots used in the work being done at Fukushima (also mentions some robots used in previous nuclear accidents).

 

[Sotan]

I found an article from Sep 2021, might be of interest for specialists. I am still reading it:
"Ten years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components"

 

[Sotan]

A new NRA meeting was held on Jan 13, 2023 to discuss the materials listed here (in Japanese).
I opened this document, which is a general review of what is known about the nuclear accident until now. I will post below the translation of a portion of this document, starting with the page numbered 26 in the PDF file. It's google translation with just a few small edits by me where the result seemed odd. The fragment presents the findings on debris at the bottom of the PCV of Unit 1, based on the investigations made up to date, and suggests/discusses 3 scenarios that are taken into consideration. The text on the 3 scenarios is presented in the post following this one, in case there is a limit in size (apologies for the length of these posts.)

Chapter 2
Behavior of the Falling Core and its Impact on the Primary Containment Vessel
Section 1 Inside the Unit 1 Primary Containment Vessel, Examination Status
2-1-1 TEPCO Report and Features

Since February, we have been taking pictures of the inside of the Unit 1 reactor containment vessel. The specific equipment, details of implementation, and photographing results are described in Attachment 4-1. Prior to this, TEPCO and IRID have taken pictures of the inside of the reactor containment vessels of Units 2 and 3. Although it is not yet sufficient due to the severity of the environment, the information obtained in the process is summarized in Attachment 4-2. The results of the photography inside the PCV of Unit 1 differed greatly from the results of photography inside the PCV of Units 2 and 3, which had already been carried out, and this attracted attention. In addition, photography of the inside of the reactor containment vessels of each unit has not progressed sufficiently, and the above understanding may change in the future.

The photographing results that attracted attention are as follows (see FIGS. 8 to 10). (See Attachment 4-3)

(1) TEPCO determined that there was a mound-like object with a height of about 1.0m, which was likely derived from the fallen molten core, near the Unit 1 pedestal opening.

(2) Concrete near the Unit 1 pedestal opening has been lost over a considerable area. On the other hand, the reinforcing bars and inner skirt that were inside the concrete have remained almost unchanged. Such a phenomenon has not been confirmed in Units 2 and 3 so far.

(3) A terraced structure was observed around the pedestal, with a height of 1.0 to 1.1m from the bottom of the primary containment vessel near the opening, and a height of 0.2 to 0.4m on the opposite side of the opening. Moreover, it seems that the concrete failure occurs only in the part below the terrace structure.

(4) Although it is a small part, a cross-sectional image of a terrace-like structure has been obtained, and a structure with bubbles can be seen, but nothing more is known about these. The thickness of the section is estimated to be approximately 3 cm. Note that the lower surface of the terraced structure appears smooth.

(5) Deposits thought to have arrived from the pedestal can be seen on the back side of the jet deflector located at the outermost periphery of the reactor containment vessel, but no major damage is seen on the jet deflector itself. As far as it can be seen, there is no major damage to the inner surface of the reactor containment vessel.

(6) It has been confirmed that the lower part of the terrace structure is hollow near the pedestal opening, but it is unknown at this stage what happens in places away from the opening. In addition, in places where there are few structures in front of the pedestal opening, the terraced structure has fallen onto the floor of the containment vessel.

(7) Metal structures such as pipes located at the bottom of the terrace structure appear to be mostly maintained. However, the RCW (Reactor Cooling System) piping near the opening is not in its original position, and its whereabouts have not been confirmed.

(8) The lead shield mats (lead wool mats) appears to have melted and fallen at the position of the terrace structure. At the top of the terrace structure, the covering material (glass fiber) of the lead shield mat (lead wool mat) seems to be maintained, and the effect of the significant high temperature seems to be limited to the vicinity of the terrace structure. In addition, TEPCO confirmed that the lead shielding was lost below the same height as the opening of the pedestal even on the opposite side of the pedestal opening.

(9) A bubble-shaped object can be seen at the pedestal opening at a height of 1.4m, but it is clear that there is a space below it. However, no information has been obtained as to what the back surface of the bubble-shaped portion looks like.

(10) Debris deposits on the floor surface of the reactor containment vessel around the pedestal are unclear, but some hemispherical objects have been photographed. (It is not clear at this stage what exactly it is.)

 

[Sotan]

(Following up from the previous post)

2-1-2 Draft Scenarios, etc. proposed by the Accident Analysis Committee (Attachment 4-3 and Attachment 5)

The investigation team is proceeding with consideration of the following three basic questions.

(1) Why does the molten core not seem to spread thinly? Conventionally, it has been thought that the molten core spreads thinly and widely. The height of the terraced structure near the pedestal opening is 1.0 to 1.1m from the bottom of the containment vessel, and although it is unconfirmed at this time, it is possible that about 1.0m has accumulated at the pedestal opening or behind it. There is a possibility that it is inconsistent with this conventional knowledge.

(2) Why was the concrete of the pedestal wall lost? Conventionally, in MCCI (Molten Core Concrete Interaction), which has been considered for safety evaluation, it is thought that molten debris of about 2000°C comes into contact with reinforced concrete and melts/damages the reinforcing bars as well. However, this time, metal structures such as rebar remain mostly intact, and the temperature seems to stay below 1000°C (not only the rebar but also the relatively thin piping around it remains in its original shape. In addition, considering the way the lead shield mats (lead wool mats) are affected, it is possible that the melted-down area is the result of 'cold' interactions, including the very close proximity of the terraces.

(3) How was the terraced structure formed? The formation process of the terraced structure is not known at this stage. Assuming that the molten debris layer exists up to the present position of the terrace structure, if the fallen molten core simply takes with it all the metal structure directly below the reactor pressure vessel (RPV), it is thought that the resulting debris it will not accumulate to such a height. The 33rd Meeting of the Accident Analysis and Investigation Committee Document 1-1 P8 states, “Even assuming that all the fuel and internal structures inside the reactor have melted, the deposition height should be about 1.1 m inside the pedestal.

The following three models were proposed to the Accident Analysis Study Group as potentially able to answer the three basic questions above. These models were presented from the perspective of promoting future discussions and experiments, and we are not at the stage where we can discuss the superiority or inferiority of the proposals at this stage.

The scenarios proposed by the accident analysis study group can be roughly divided into the following three types:
A: Concrete melting model at high temperature
B: Concrete dissolution model in water
C: Molten core expansion model due to gas

A: Concrete melting model at high temperature (Attachment 5)
- The molten core falls into the pedestal and spreads outside of it through the pedestal opening.
- The melted material raises the temperature of the concrete, and the concrete melts.
- A crust is formed, causing concrete damage and cavities when the melt contents inside move on.

Through the above process, it is believed that the falling core melted material raised the temperature of the concrete near the pedestal opening, resulting in concrete failure and the formation of table-like deposits. In this scenario only the concrete failed because the temperature of the concrete did not reach the melting temperature of the rebar.

B: Concrete dissolution model in water (Attachment 5)
- Water temperature and pressure rise locally due to core meltdown falling in an environment where water or steam exists in the pedestal.
- Concrete is damaged by dissolution of concrete components in high-pressure water. A highly viscous liquid phase is formed consisting of concrete components and a large amount of water. As the water temperature rises and the local pressure is released, the water evaporates and the dissolved concrete components solidify while foaming.
- More water evaporates, creating cavities at the bottom of the condensate. Through the above process, the fallen core melt generates high-temperature water or steam, which reacts with the concrete components to break the concrete and create a highly viscous liquid phase that is the source of table- (terrace-)like deposits. Water at high temperature and pressure is known to dissolve rocks, especially SiO2 in rocks. Concrete is composed of aggregate and cement, and if the aggregate contains a lot of SiO2, the aggregate in concrete may dissolve in high-temperature, high-pressure water. It is also known that glass containing a large amount of water, which is produced by the reaction of high-temperature, high-pressure water and SiO2, expands and becomes porous when the water evaporates. A similar phenomenon may have occurred in the reactor, resulting in the formation of terrace- or table-like deposits.

C: Molten core expansion model due to gas

The fallen molten core appears to form a 1m-high bulge at the back of the pedestal opening, and it is highly likely that it also spreads to the outer periphery of the pedestal. On the other hand, the bulge within the pedestal does not currently appear to fill the pedestal. If it is confirmed that a bulge is formed, there are two possibilities considered at the present, one being that the viscosity of the fallen core was high [and somehow led to such formations], and another is that gas ejection left such structures after the fallen core accumulated to some extent at the bottom.

After that, it is thought that the dropped molten core passed through the pedestal opening and gradually flowed out to the outer periphery of the pedestal. The degree of spreading cannot be determined without additional information from internal vessel investigations that will follow.

The energy / heat (including the effects of gamma rays) from the radiant core from the molten core increased the temperature of the pedestal wall, causing the concrete to decompose, lose its strength, and become powdery. Mechanisms for loss of strength include desorption of calcium and generation of stress due to phase changes in crystal components in the concrete. A radiation-induced warming failure mechanism does not require direct contact between the molten core and concrete and may explain why so little solidification of the molten core is found in the remaining rebars of the pedestal walls. In addition, it is known that the compressive stress of concrete is greatly reduced in the above reaction at around 700 to 1000℃. It may be reasonable to think that the concrete with reduced cohesive strength was washed out after the alternative water injection got into full swing.

When the pedestal floor or pedestal wall reacts with the molten core, carbon dioxide and water vapor are generated. Cooling water that leaked from the core (thought to be limited in quantity) may also have been involved. These gas-rich layers (hereafter referred to as “swollen layers”) are sometimes referred to as “swelled melt” in MCCI-related literature, but since the experimental conditions vary greatly it is not clear whether it refers to exactly the same phenomenon.) It is unclear whether such layers were integrated with the molten core body or present as a separated layer, but here we are thinking of it as a separated state (like in an image of beer foam) . At present, the temporal relationship between the outflow of the molten core from the pedestal opening and the formation of the "expansion layer" is unknown.

Components containing silicon separated from the concrete located at the top of the "expansion layer" to form a sort of film or layer. It is conceivable that this film solidifies due to factors such as a temperature drop and adheres to the surrounding pipes and equipment. The phenomenon of sticking to pipes, etc. is a phenomenon called "anchoring" in previous MCCI experiments, but it has not been confirmed whether it would have occurred reliably under the conditions of this time. It is also possible that some of the powdered concrete deposited on top of this film and facilitated its formation. It should be noted that the adhered membranes/layers seen in past MCCI experiments are relatively fragile, and in open spaces such as the front of the pedestal opening, where there are no pipes for "anchoring", it is quite possible that such a layer will collapse. Also, the "thin membrane" contains many air bubbles and can be quite insulating. If so, it may explain that the concrete failure is confined to the bottom of this 'thin film'.

After that, due to the decrease in decay heat and the progress of alternative water injection, the temperature of the "expansion layer" dropped and contraction occurred, leaving only the "thin membrane" in its original position. It should be noted that if a crack occurs in the "thin film" during the growth process of the "expansion layer", it is quite possible that the "expansion layer" and the "thin film" will be formed on top of it. It may be possible to explain this way that there are places where the terraced structure is multi-layered.

It may be unlikely that a “thin film” (terrace-like structure) remains in the pedestal at a height of about 1 m. While the diameter of the pedestal is about 6m, it seems that there are not many pipes that can serve as anchoring at a height of about 1m. Furthermore, it is believed that a considerable amount of water flowed down from the damaged part of the pressure vessel to the pedestal when the alternative water injection got into full swing.

 

[Sotan]

New article (from 5 days ago) on the IAEA site about recent developments at Fukushima Daiichi.
It contains a link to a new report from the Government of Japan which "summarizes the events and highlights the progress related to recovery operations at the Fukushima Daiichi Nuclear Power Station." The report covers the developments up to September 2022 so it's not very up to date but it's a good lecture and... it's in English.

 

[Sotan]

- A report published on April 4 by Tepco includes many photos taken inside the pedestal of Unit 1 showing the inner walls of the pedestal with exposed rebar but also debris presumed to be CRD housings, CRD housing supports and CRD's, together with more rubble-like and lumpy deposits.

 

[Sotan]

An even better report published on Apr 24 on the NRA meetings page.
(Using the page numbers printed at bottom right in the PDF file)

- Most impressive, on page 11 you can see a panorama stitched from photos taken inside the pedestal of Unit1.

- Page 3: Steel bars exposed, "about 1 m above the floor" - not clear if the mean the whole 1m from floor up or just a smaller region in the area of the 1m height level. (A full 1m of concrete missing somehow seems a lot to me, but I suppose it's possible.) Still, they seem happy that the bars do not seem melted or deformed, they even preserve the striations from factory (Photo 2). Suggesting they still support the RPV weight well. A fallen CRD housing in Photo 3. Photo 3 also shows a remaining portion of "terrace-" or "shelf-shaped" debris, which I imagine is part of the crust formed after the solidification of the molten innards of the reactor. Above that shelf-shaped debris the concrete of the pedestal walls is still in place.

- Page 5: At the bottom of the pedestal the largest fallen structural components identified appear to be CRD housings. In particular, the "CRD replacement machine" (can't remember the correct term. CRD exchanger?) main assembly was not visible, only part of its rails and (a) wheel. All around there is debris, as high as ~1m, and fallen structural components such as CRD housings can be identified.

- Page 6: Looking up in the pedestal. CRD assemblies can be seen. Some of them seem displaced, being lower than originally (also shown on Page 23 Photo 3). Some of them have fallen. Around the point indicated by number 7 a "black spot" appears (Photo 2) where normally should have been some CRD unit; it is possible that this is a hole in the RPV bottom.

- Page 7 gives a photo of the area before the accident.

- Page 8: again, looking up in the pedestal. A stream of water drops are falling up from above, in an area roughly in the center of the pedestal (Photo 1), creating a foamy patch on the surface of the water. Probably flowing through the breach of the RPV bottom. In the area of the opening used by the CRD exchanger there appears to be a fallen CRD housing, it will need to be taken in consideration (as an obstacle, I guess?) for the planning of next investigations or debris removal operations.

- Page 11 - the "panorama". (After that there are a number of pages with photos already reported before.)

- Page 24-25 - a comparison with other units. Unit 1 was without cooling for the longest time so it is assumed to be the worst affected. The photos on these pages seem to support that assumption.

 

[Rive]

Thank you for still following the topic and providing updates on the situation.

 

[Sotan]

* Article in Asahi (google translated) reporting the request from Nuclear Regulation Authority to TEPCO "to evaluate the impact of radioactive material scattering outside the site, including the possibility of a hole (that might occur) in the containment vessel due to subsidence of the pressure vessel (for example in case of an earthquake), and to consider countermeasures". NRA is not convinced of TEPCO's optimist conclusion that the pedestal of Unit 1 is still able to support the reactor vessel in case of a large earthquake.

* There are many articles (like here or here or here) about the upcoming release of tritiated water from Fukushima into the ocean. All the work needed (including an underground tunnel) for this purpose has been done and efforts are being made to convince the public that the release is safe. IAEA representatives are visiting the site these days and IAEA is planning to issue a final report next month.

 

[etudiant]

* Article in Asahi (google translated) reporting the request from Nuclear Regulation Authority to TEPCO "to evaluate the impact of radioactive material scattering outside the site, including the possibility of a hole (that might occur) in the containment vessel due to subsidence of the pressure vessel (for example in case of an earthquake), and to consider countermeasures". NRA is not convinced of TEPCO's optimist conclusion that the pedestal of Unit 1 is still able to support the reactor vessel in case of a large earthquake.

* There are many articles (like here or here or here) about the upcoming release of tritiated water from Fukushima into the ocean. All the work needed (including an underground tunnel) for this purpose has been done and efforts are being made to convince the public that the release is safe. IAEA representatives are visiting the site these days and IAEA is planning to issue a final report next month.

I'm really surprised that the Japanese government is so determined to dump the Fukushima water immediately.
It is less than 2 million tons, so a dozen tankers would easily hold all of it in safe storage, at a construction cost of a few billion dollars at most, a trifle compared to the overall cost of the. cleanup.

Japan is clearly interested in reopening its nuclear power segment. That will be made easier if there is no new nuclear pollution event such as the dumping of this contaminated water. Instead, move the tankers to some non typhoon susceptible location for a few decades to allow further tritium decay, thereby defusing the issue entirely
Afaik, The area around Christmas Island is one such location and I'm sure a long term anchorage could be arranged reasonably cheaply, with due provisions for ongoing maintenance and supervision.

 

[Astronuc]

13 years after meltdown, the head of Japan’s nuclear cleanup is probing mysteries inside reactors​

https://apnews.com/article/japan-fu...tdown-debris-ae9cea4db2a839b7fe4a8c53f22f3fd7

Yes - we need samples of what is left of the damaged fuel, otherwise, we are simply speculating based on indirect evidence. At TMI, cameras were lowered into the core and it was clear that some chemical interaction and possible melting has occurred in the fuel. Fuel samples were collected and analyzed. TMI-2 is still sitting there with contamination. When I was at the site in the 1990s, it was still too radiologically 'hot' to enter.

https://en.wikipedia.org/wiki/Three_Mile_Island_Nuclear_Generating_Station#Decommissioning

Soluble fission products may permeated the concrete, which make decommissioning challenging.

 

[Vanadium 50]

Soluble fission products may permeated the concrete, which make decommissioning challenging.

I assume you're worried about cesium and strontium? Presumably dissolved in the water and exchanged with water in the concrete?

If so, isn't that a good thing? It's already partially sequestered. Spray some plastic sealant on it and dispose of it.