Japan Earthquake: Nuclear Plants at Fukushima Daiichi

In summary: RCIC consists of a series of pumps, valves, and manifolds that allow coolant to be circulated around the reactor pressure vessel in the event of a loss of the main feedwater supply.In summary, the earthquake and tsunami may have caused a loss of coolant at the Fukushima Daiichi NPP, which could lead to a meltdown. The system for cooling the reactor core is designed to kick in in the event of a loss of feedwater, and fortunately this appears not to have happened yet.
  • #3,676
elektrownik said:
New thermal images, very bad, so hot: http://www.mod.go.jp/j/approach/defense/saigai/tohokuoki/kanren/230414.pdf

Please not the scale of the temperature. Nothing is very hot.
 
Engineering news on Phys.org
  • #3,677
Maxion said:
Please not the scale of the temperature. Nothing is very hot.
Look at the right column: some temperatures are rising quite a bit.

Also, some hot spots are too small on the detector to resolve the real temperature.
The are measuring from 3000 ft high, and do not dare to take a closer look.
 
  • #3,678
tsutsuji said:
A research team from Kyoto, Hiroshima, Kokugakuin, Nihon universities presents its "Interim Report on Radiation Survey in Iitate Village area conducted on March 28th and 29th" : http://www.rri.kyoto-u.ac.jp/NSRG/seminar/No110/Iitate-interim-report110404.pdf. It includes a gamma ray radionuclide analysis of soil samples.

Thanks, tsutsuji ! This pointed to the level triggering actions in case of radiation exposure. I later found http://www.jnes.go.jp/bousaipage/english/an-3-12.htm" :
  • For an estimated exposure between 10 and 50 milliSieverts (per year I guess), people should shelter in door
  • Above estimated annual dose of 50 milliSieverts, people should shelter in concrete building or evacuate

Well with the provided report, I was able to do a calculation of the hour dose on today that would trigger either the first or second action.

WARNING : This calculation is based on readings on graphs in the report, so there could be some errors. It is also an extrapolation of measurements in Iitate.

Projected total dose after 84 days would be 96 miiliSieverts in Magata, 62 milliSieverts after 42 days (graph page 6). After 21 days, I considered the dose linear in time. That would lead to a total of 323.47 milliS in Magata in one full year (96 up to day 84, then prorata, approx 0.80 per day)

To reach 50 milliS per year, this is a factor of 6.47. Reading at Magata on March 31st was 24 microSieverts per hour. Assuming the rate fell by decay from a 10/13 factor (reading on graph page 5 - not very accurate) till now, reading at Magata today should be around 18.46 microSieverts per hour.

Therefore, applying the 6.47 factor, the hourly limits today should be :
  • Above 2.85 microSieverts per hour : shelter in concrete or evacuate
  • Above 0.57 microSieverts per hour : shelter indoor

Now if all this is accurate, look at thehttp://www.mext.go.jp/component/english/__icsFiles/afieldfile/2011/04/14/1304852_041319.pdf" , and determine which area should have received action 1 or 2. Fukushima inhabitants would have been told to stay indoor.

Any comments ?
 
Last edited by a moderator:
  • #3,679
Except that is BS because it is doses for the corpses who don't breathe etc. In short, for the people who'd really remain indoors as ordered and die of starvation or lack of water. It's really wrong to calculate this stuff to 2 digits accuracy. The radiation levels (see current chernobyl levels thread) vary a LOT between locations within same city block (middle of road, drain, roadside, may differ by order of magnitude). Bottom line is - they should of evacuated a lot of people they didn't evacuate, and they did evacuate a lot of people they did not have to evacuate.
edit: also, where the hell is US radiation measurement plane that US offered a few weeks ago? WTF guys. Is there some reluctance of government to use such plane and admit to the people that they're nowhere as prepared as other countries? Are they opting not to do such measurements and pretend they do everything they could?
 
Last edited:
  • #3,680
Worst case scenario Fukushima fuel pool with plutonium catches fire

http://energheia.bambooz.info/index.php?option=com_content&view=article&id=168%3Aworst-case-scenario-fukushima-fuel-pool&catid=60%3Avideo&Itemid=85&lang=it

http://vimeo.com/22352930
 
Last edited by a moderator:
  • #3,681
Can someone please be so kind and repost the link to the large cross-sectional plan of the nuclear reactor that was posted some time ago, not the GE handout - I tried very hard and cannot find it
 
  • #3,682
AntonL said:
Can someone please be so kind and repost the link to the large cross-sectional plan of the nuclear reactor that was posted some time ago, not the GE handout - I tried very hard and cannot find it

this one? http://fukushimafaq.wikispaces.com/Reactor+Blueprints
 
Last edited by a moderator:
  • #3,683
bytepirate said:
#4 was undamaged after #3 exploded: http://www.digitalglobe.com/downloads/featured_images/japan_earthquaketsu_fukushima_daiichi_march14_2011_dg.jpg

there also seems to be no truck at no. 4 at that date, while later on there was one.
 
Last edited by a moderator:
  • #3,684
bytepirate said:
this one? http://fukushimafaq.wikispaces.com/Reactor+Blueprints

yes - you are a star - thanks
 
Last edited by a moderator:
  • #3,686
Much more likely to be beams from structures on the harbourfront that were obliterated by the tsunami.
 
  • #3,687
bytepirate said:
#4 was undamaged after #3 exploded: http://www.digitalglobe.com/downloads/featured_images/japan_earthquaketsu_fukushima_daiichi_march14_2011_dg.jpg

Doesn't it look like as if there's white smoke coming from the eastern (sea) side of unit 4?
 
Last edited by a moderator:
  • #3,688
Krikkosnack said:
Fuel Rods of the reactor 4... are really those?
http://www.houseoffoust.com/fukushima/rods.html
Most of those pictures do not point to fuel rods, which are slightly less than 0.5 inch in diameter. The top images show a 9x9 fuel assembly.
 
Last edited by a moderator:
  • #3,689
clancy688 said:
Doesn't it look like as if there's white smoke coming from the eastern (sea) side of unit 4?
That smoke is continuous with the smoke towards bottom right of picture towards the trees. I guess just an eddy a few moments earlier from the #3 plume.
 
  • #3,690
Hi all. I've been reading quietly, but I wanted to contribute here since I've been keeping up with the disaster through the Japanese media.

This was posted shortly ago, I don't know if it's good news or not. But curious what people think of it. The translations are my own and while it's not perfect (I'm not a professional or a native speaker), the news is about an hour old.

http://www.yomiuri.co.jp/science/news/20110414-OYT1T00938.htm?from=main4
溶融燃料「粒子状、冷えて蓄積」1~3号機分析
Melted/fused fuel, "has grown cool and accumulated in a grain like state", analysis of Unit 1-3

注水冷却が続けられている東京電力福島第一原子力発電所1~3号機について、日本原子力学会の原子力安全調査専門委員会は14日、原子炉などの現状を分析した結果をまとめた。
About the pouring water refrigeration situation at TEPCO Fukushima Daiichi Nuclear Power Plant Units #1~3, members of the Japan Atomic Mechanics Society(?)'s Nuclear Power Safety Investigation Advisory Committee has compiled the analysis of the nuclear reactor's present condition.

 3基は核燃料の一部溶融が指摘されているが、専門委は「溶融した燃料は細かい粒子状になり、圧力容器の下部にたまって冷えている」との見解を示した。
The 3 groups have pointed out that while there is indication that partial melting has occurred, the professional committee is of the opinion that "the melted fuel has become fine grain, and has collected at the bottom of the pressure vessel and has grown cold".

 専門委では、東電や経済産業省原子力安全・保安院などが公表したデータをもとに、原子炉の状態を分析した。
The professional committee, using the data made available by TEPCO, METI, NISA etc, have made an analysis of the nuclear reactor's current state.

 それによると、圧力容器内の燃料棒は、3号機では冷却水で冠水しているが、1、2号機は一部が露出している。1~3号機の燃料棒はいずれも損傷し、一部が溶け落ちている。溶融した核燃料は、冷却水と接触して数ミリ以下の細かい粒子に崩れ、燃料棒の支持板や圧力容器下部に冷えて積もっていると推定している。これは、圧力容器下部の水温が低いこととも合致している。沢田隆・原子力学会副会長は「外部に出た汚染水にも、粒子状の溶融燃料が混じっていると思われる」と説明した。
According to this, regarding the fuel rods inside the pressure vessel container, in number 3 they have been submerged with coolant, however 1 and 2 has been partially exposed. In addition, 1~3 fuel is damaged, partially melted and then falling. They assume the melted fuel is then coming into contact with the coolant and crumbling to particles/grain no bigger than several millimeters, and collecting at the bottom of the pressure vessel or fuel rod support board/planks. It has been agreed that the water temperature at the bottom of the pressure vessel is cold. The Atomic Mechanics Society President explained that in the contaminated water going to the outside, particle sized melted fuel is thought to be mixed in with it.

(2011年4月14日21時02分 読売新聞)
April 14th, 2011 21:02 Yomiuri Shimbun

Source: http://www.yomiuri.co.jp/science/news/20110414-OYT1T00938.htm?from=main4
 
Last edited by a moderator:
  • #3,691
Sr-89 and Sr-90 activities are being reported (http://www.enewspf.com/latest-news/...-nuclear-accident-13-april-2011-1430-utc.html):

MEXT reported on measurements of strontium-89 (half-life: 50.5 days) and strontium-90(half-life: 28.8 years) in three samples taken in one village in the Fukushima prefecture on 16 March. The activities in soil for Sr-89 ranged from 13 and 260 Bq/kg and for Sr-90 between 3.3 and 32 Bq/kg. Sr-90 was also distributed globally during nuclear weapons' testing in the atmosphere, typical global levels of Sr-90 in surface soils are in the order of one to a few becquerel per kg. Strontium was also measured in plant samples in four others villages, with values ranging from 12 to 61 Bq/kg for Sr-89 and 1.8 to 5.9 Bq/kg for Sr-90.

As a first impression, the reported activity ratio of Sr-89 to Sr-90 (of the order of 10:1) seems rather low for reactor fuel with the burnups one would assume for core average at 3 - 4 months into the cycle. I would have assumed the ratio to be somewhat higher - perhaps 15 : 1 or so, but then again: from what I've been told, Sr activities are pretty difficult to measure accurately.

Would someone happen to have burnup calculation results regarding Sr89/90 ratio for 8x8 or 9x9 BWR fuel as a function of exposure? It might be worthwhile to compare the ratios obtained by using different lattice codes & CS libraries, and different assembly designs (not knowing what they actually used at Fukushima).
 
Last edited by a moderator:
  • #3,692
georgiworld said:
I wonder if someone can clear something up for me. From the beginning I thought Reactor 4 posed the most danger since the fuel in it, both spent and unspent, were outside of containment. Since then most attention has focused on the three other reactors and the possible breaching of the RPV with a concomitant oozing of corium .

There have now been reports of fires at number 4, which has refocused attention on it and which concerns me greatly.

As I understand it, the decay heat that is emanating from the spent fuel has created the need for a great deal of water to be added in order to remain cool. While this effort appears to have worked since there remains water in the pool, the amount of heat generated maybe too much to deal with and the excess heat has found another outlet.

Now what I'd like to know is could this heat be melting the unspent fuel rods? Is that what is on fire?

Are we looking at an open-air reactor with widespread dissemination of radiation?

Can anyone reassure me that this is not the case.
The decay heat was stronger in the cores of Units 1, 2 and 3, because they had recently shutdown (May 11). They then lost cooling on May 12-13. Unit 4 had been shutdown for about 100 days (Nov 30, 2010 - Mar 11, 2011), so the decay heat was significantly diminished. However, there is still heat on the order of 0.2% of operating power, or about 3.7 MW. That is still a significant amount of heat.

The SFP lost cooling so there was not removal of heat by the normal closed loop, but instead without cooling the SFP water increased in temperature to the point were it would start to evaporate at a higher rate. In addition, without good circulation, the relatively stagnant pool water has very low heat transfer coefficient, so the water next to the fuel rods could boil. It is also possible that the SFP may have cracked somewhere because of the seismic loading (but this is not known or confirmed).

It is surmised that the cladding of the spent fuel in SFP #4 oxidized to the point of rupture, thus releasing fission gases (radioisotopes of Xe, Kr), and some volativles I, Cs. Fuel particles would be released only if the cladding split open, or experienced circumferential fractures - which would be possible if there was excessive hydriding of the cladding. The hydrogen is generated from the reaction of Zr + 2 H2O => ZrO2 + 2 H2, which is basically a corrosion reaction. Normally it occurs at a very slow rate of several microns per year. The corrosion rate increases exponentially with temperature of the metal-oxide interface. Normal operating temperatures are on the order of 300C, but it is possible that higher temperatures are achieved if the cooling is inadequate. What temperatures the fuel actually experienced has yet to be determined, and it requires a forensic analysis, particularly an evaluation of the damage, oxidation and cladding microstructure in connection with compuational analysis with appropriate CFD tools.
 
  • #3,693
AntonL said:
Fuel in pool: 1331 spent fuel assemblies and 204 brand new assembles and some of them simply gone critical.
I already can hear Gunderson reporting that unit 4 is an open air reactor.

However let's analyse SPF 4
Capacity = 1425 m3 http://www.nisa.meti.go.jp/english/files/en20110406-1-1.pdf"

Decay Heat:
2000kW for spent fuel from unloaded reactor last operation 29 Nov 2010 (can be calculated)
+ 400kW long term stored spent fuel (estimated on the high side)
2400kW total

Assuming SPF4 was at 30oC
To raise 1425m3 by 70oC using 2.4MW it would take 48 hours
so SPF 4 has started to boil somewhere between March 13 afternoon to March 14 morning.

The pool is about 11 metres deep,
so to boil away 1 metre or 1425/11= 129.5m3 of water using a 2.4MW heater 33.8 hours
I cannot find the detail drawing that was posted here before to confirm the depth so I took depth of SPF 7

From earthquake (3pm 11/3) to unit 4 explosion (6am 15/3) if I can calculate correctly are 87 hours,
thus about (87-48)/33.8 = 1.2 metres of water would have boiled away at time of explosion.
that is the 4 metre fuel rods have 5.8m water covering them -
so where does the Hydrogen come from??

Helicopter crews on 17 March reported spotting water in SPF4 thus they concentrated on
dropping water on unit 3 - proof that there is ample water in the pool.

Spraying water into unit 4 was only started on March 20 at 9:40 thus
at time of explosion 6am 15/3 water level -1.2m
10am 20/3 114 hours later a further level drop of 3.4 metres due to boiling
thus when water spraying started on 20March the level was down 4.6 mtres
excluding leakage or spillage, this leaves the 4 metre fuel rods 2 metres under water.
Tepco set their priorities correctly and started spraying water at the right time.

http://www.nirs.org/reactorwatch/accidents/6-1_powerpoint.pdf" that the storage capacity of all fuel pools at Fukushima as 8310 fuel assemblies,
that is 1444 fuel assemblies can be stored at each units 2 to 5, based on SFP volume.

However, SPF4 had 1331+204 = 1535 fuel assemblies stored which is more than stated capacity! http://www.nisa.meti.go.jp/english/files/en20110406-1-1.pdf"

Therefore we can speculate that Tepco double layered at least two or three spent fuel racks,
this would explain the early exposure of fuel to air, hydrogen generation, fuel damage etc.
and we can speculate that two or three racks worth of spent fuel may be destroyed.

Debunk that. :biggrin:
Have I solved the hydrogen, spent fuel pool water mystery?

Now, should my calculation and speculation be proven true, Tepco needs to do a lot of explanation.

Let's please stop this discussion about "double layers" of fuel in the SFP. The depth of the fuel pool is about 40 ft and the height of a fuel assembly in the SFP racks is about 14 ft. Plant technical specifications require a minimum water level of about 20 ft above irradiated fuel in the SFP. This technical specification requirement could never be met if two fuel assembilies were stacked on top of each other. The very idea of such a thing would be impractical.
When a utility increases the capacity of the SFP, they do it by replacing the exisiting used fuel storage racks in the SFP with racks that allow the fuel to be placed closer together (higher density). The geometry is analyzed and possible change to the neutron absorber panels in the fuel racks are changed to preclude criticality of the assemblies in the SFP.

Back to loss of inventory in the U4 SFP: AntonL's boiloff calculations look pretty good. There probably was also several feet (maybe 3-4 ft total) of SFP inventory loss due to pool sloshing during the earthquake. However, the inventory boiloff plus the inventory loss from sloshing wouldn't explain uncovery of the irradiated fuel in the U4 SFP. It is possible that the earthquake caused a leak in the spent fuel pool (perhaps in the gate plugs that are removed when performing refueling operations between the reactor and the SFP). Such a leak, if large, would explain the additional inventory loss. However, the limited photos of the damage to the U4 reactor indicate that there was a VERY hot fire with explosions in the lower levels of the U4 reactor building. How H2 generation and ignition at the elevation of the U4 refuel floor caused this lower building destruction is beyond me.
 
Last edited by a moderator:
  • #3,694
SayaX said:
Hi all. I've been reading quietly, but I wanted to contribute here since I've been keeping up with the disaster through the Japanese media.

This was posted shortly ago, I don't know if it's good news or not. But curious what people think of it. The translations are my own and while it's not perfect (I'm not a professional or a native speaker), the news is about an hour old.
I don't believe the fuel necessarily melted. It certainly did have contact with the coolant, then seawater. Various chemical reactions are possible well below melting temperatures. It is certainly likely that the Zr-alloy cladding was several corroded (oxidized), which is the source of hydrogen. The oxidation could have proceeded to cladding rupture and perforation (breach), and possibly fracture or cracking. If cracking occured, particularly axial splits, then the fuel has intimate contact with the coolant, and it is possible that the ceramic fuel oxidized, possibly to the point where particles of fuel dropped out and settled to the bottom of the core, or perhaps in the regions below the core.

If there has been water in the bottom half/third of the core, then melting is not necessarily an outcome (it might if temperatures were sufficiently high). On the other hand, dissolution of the fuel (to some extent) would certainly occur if there was large scale failure of the cladding.
 
  • #3,695
Wild theory: could SFP4 have gone critical, after damage to the fuel rods spewing the fuel pellets that fell down? Then, a powerful excursion deep under water (perhaps with positive 'damage coefficient' so to say, when steam generation in one place makes criticality worse elsewhere) *shook* the spent fuel pool, damaging the walls as by man-made quake? The water around would of acted as sort of tamper, preventing quick formation of steam bubbles and even redistributing pressures between bubbles, potentially leading to instability. To think about it, it could have experienced a power excursion, followed by formation of voids and lifting of water, then the voids could collapse as the water was falling down.

(I presume cladding entirely destroyed unless shown otherwise, as the reaction of zirconium with steam is exothermic, and with air, even more so, and as is the reaction of zirconium with uranium dioxide. Simply put, it is fire - or if you wish, exothermic reactions that speeds up at higher temperatures. To call it oxidation is true but makes it into a sort of under-statement)
 
Last edited:
  • #3,696
Thank you Astronuk, as always your technical assessment is spot on.

My question however is not about what happens to the cladding of the spent fuel but what effect the heat will have on the unspent fuel which was stored in SPF#4. Now while the decay heat was greater in the reactors that were operational at the time of the incident, it was contained in the RPV.

My fear is that the unspent fuel in the SFP of #4 will go critical. Is that possible?
 
Last edited:
  • #3,697
georgiworld said:
Thank you Astronuk, as always your technical assessment is spot on.

My question however is not about what happens to the cladding of the spent fuel but what effect the heat will have on the unspent fuel which was stored in SPF#4. Now while the decay heat was greater in the reactors that were operational at the time of the incident, it was contained in the RPF.

My fear is that the unspent fuel in the SFP of #4 will go critical. Is that possible?
The spent fuel pool racks are design to prevent criticality. There is neutron absorber material present. IF somehow that neutron absorber material was lost, then there would be a chance of criticality. The configuration of the pool is important. It's not clear to me where the fresh fuel was located with respect to the reinsert and discharge fuel.

Even if the SFP went critical, this does not necessarily lead to an explosion. An explosion requires a rapid release of energy, and that doesn't happen if a system is critical (k = 1) or slightly supercritical (k > 1, but < ~1.006).

The fresh fuel would have no fission products, and no decay heat. Except for criticality, it would be pretty benign. Even if fresh fuel went critical, there would be no fission product accumulation, unless it was critical for many days or weeks, but the fission product inventory would not be significant. The problems at Unit 4 were only days after losing cooling.
 
  • #3,698
georgiworld said:
Thank you Astronuk, as always your technical assessment is spot on.

My question however is not about what happens to the cladding of the spent fuel but what effect the heat will have on the unspent fuel which was stored in SPF#4. Now while the decay heat was greater in the reactors that were operational at the time of the incident, it was contained in the RPV.

My fear is that the unspent fuel in the SFP of #4 will go critical. Is that possible?
I think it gone critical before, after geometry change due to the fire. The geometry has to be specifically designed as to avoid criticality. The pool was re-racked to higher capacity.

Possible, definitely it is possible, did it happen, we can't know for sure (lack of good data), will it happen, we can't know either.

Things to know about criticality:
  1. The criticality in the fuel of that reactor type is not possible without moderator to slow down neutrons (water is moderator). The enrichment must be greater than 6% to allow criticality without moderator.
  2. thus, there, fast criticality (without moderator, on fast neutrons) is impossible (unless some process separates plutonium and uranium, seems unlikely).
  3. The temperature increase of the fuel leads to Doppler broadening of the absorption of neutrons by U238, decreasing the reactivity. This limits the temperature.
  4. Thus, the criticality does not imply nuclear explosion
You can look at the list of criticality accidents here:
http://www.johnstonsarchive.net/nuclear/radcrit.html
to know what to expect.
The criticality is not hell on Earth event. In all the mess, it could even be going on somewhere unnoticed. It's not necessary a kaboom, even though it might be a kaboom.
 
Last edited:
  • #3,699
Thanks for the link to blueprint for reactor building 1: http://fukushimafaq.wikispaces.com/Reactor+Blueprints

The reactor buildings of nos 2,3,4 are different: bigger in their horizontal dimensions and placed differently in respect to the corresponding turbine buildings.

Has anyone seen a blueprint for the no4 reactor building? How does the internal layout look like? Can one assume that 2,3,4 share a common internal layout?

Another thing: An annotation to picture http://i306.photobucket.com/albums/nn270/tcups/r735227_5964756.jpg of https://www.physicsforums.com/showpost.php?p=3196018&postcount=463 mentions thermal damage (from fire?) to the northside upper part of No.4. Has this been confirmed? To me that would explain that aspects of no4 damage that are bound inwards.

BTW Thanks to all contributing, have been reading here for the last week. And sorry if my question is noobish. I'm just an amateur trying to understand what's going on.
 
Last edited by a moderator:
  • #3,700
Anyone have any thoughts on collapsing the fukushima power station into the pacific with this techinque:

http://youtu.be/S1f6vbiuUt0
http://youtu.be/l5jfaXSFfGQ

Just the thought of these reactors and all that stored waste spewing radiation into the atmosphere for who knows how long...well its just damn scary
Instead of trying to bring the pacific to the reactors put the reactors in the pacific.
At that point the release of radiation into the atmosphere will cease and men could clean it up using deepsea salvage operations.
maybe even build a cofferdam around the whole damn complex like this:

http://youtu.be/2kxVKkXW5Fg
 
  • #3,701
michael200 said:
Let's please stop this discussion about "double layers" of fuel in the SFP. The depth of the fuel pool is about 40 ft and the height of a fuel assembly in the SFP racks is about 14 ft. Plant technical specifications require a minimum water level of about 20 ft above irradiated fuel in the SFP. This technical specification requirement could never be met if two fuel assembilies were stacked on top of each other. The very idea of such a thing would be impractical.
When a utility increases the capacity of the SFP, they do it by replacing the exisiting used fuel storage racks in the SFP with racks that allow the fuel to be placed closer together (higher density). The geometry is analyzed and possible change to the neutron absorber panels in the fuel racks are changed to preclude criticality of the assemblies in the SFP.

Back to loss of inventory in the U4 SFP: AntonL's boiloff calculations look pretty good. There probably was also several feet (maybe 3-4 ft total) of SFP inventory loss due to pool sloshing during the earthquake. However, the inventory boiloff plus the inventory loss from sloshing wouldn't explain uncovery of the irradiated fuel in the U4 SFP. It is possible that the earthquake caused a leak in the spent fuel pool (perhaps in the gate plugs that are removed when performing refueling operations between the reactor and the SFP). Such a leak, if large, would explain the additional inventory loss. However, the limited photos of the damage to the U4 reactor indicate that there was a VERY hot fire with explosions in the lower levels of the U4 reactor building. How H2 generation and ignition at the elevation of the U4 refuel floor caused this lower building destruction is beyond me.

Ok, michael200, I take your point on doubling up so let's forget it. Thanks for sort of agreeing with my boiloff calculation and let's asume there was no leak in pool otherwise Tepco could not have waited until the 20th to replenish water, because should there have been a significant leak fuel exposure would have resulted before then.

But where does the Hydrogen come from for the explosion, forum members here agree that the explosion centre was lower down in the building on the north side, which does make sense because of the observed damage.

For that scenario I can also give a very imaginative explanation. When unit 3 was vented, could unit 4 have pumped hydrogen steam into unit 3. Unit 3 and 4 share a common exhaust stack and there was no power for fans to work to aid the exhaust procedure, Furthemore, we do not know if there are any dampers in the system and if installed I would imagine they fail open when power is lost.

Lets assume unit 3 pumped unit 4 full of steam and hydrogen, this would then be into the suppression chamber, then H2 will leak into the primary containment chamber, it would not immediately escape to the roof, as there is a seal between the reactor vessel and PCV so that PCV is not flooded during fuel transfer. The Hydrogen could have leaked out through the access hatch which would not have been sealed due to the maintenance taking place, This access hatch is on the ground floor, which is the right level for a lower explosion centre. The only question why the long delay between units 3 and 4 exploding.

@TCups have you considered that the access hatch could also have leaked at unit 3, this could explain a second and third explosion. Explosion 1 roof area, due to shock wave and vibration of the building the access hatch leaks and PCV burps through access hatch, now more hydrogen in lower building resulting in explosion 2, same happens again explosion 3 and PCV has lost a lot of pressure and the process stops, looking at the devastation on lower northern side this could work, also watch the video to the north a low level dust cloud expands further and faster than to the south
 
Last edited:
  • #3,702
AntonL said:
Ok, michael200, I take your point on doubling up so let's forget it. Thanks for sort of agreeing with my boiloff calculation and let's asume there was no leak in pool otherwise Tepco could not have waited until the 20th to replenish water, because should there have been a significant leak fuel exposure would have resulted before then.

But where does the Hydrogen come from for the explosion, forum members here agree that the explosion centre was lower down in the building on the north side, which does make sense because of the observed damage.

For that scenario I can also give a very imaginative explanation. When unit 3 was vented, could unit 4 have pumped hydrogen steam into unit 3. Unit 3 and 4 share a common exhaust stack and there was no power for fans to work to aid the exhaust procedure, Furthemore, we do not know if there are any dampers in the system and if installed I would imagine they fail open when power is lost.

Lets assume unit 3 pumped unit 4 full of steam and hydrogen, this would then be into the suppression chamber, then H2 will leak into the primary containment chamber, it would not immediately escape to the roof, as there is a seal between the reactor vessel and PCV so that PCV is not flooded during fuel transfer. The Hydrogen could have leaked out through the access hatch which would not have been sealed due to the maintenance taking place, This access hatch is on the ground floor, which is the right level for a lower explosion centre. The only question why the long delay between units 3 and 4 exploding.

@TCups have you considered that the access hatch could also have leaked at unit 3, this could explain a second and third explosion. Explosion 1 roof area, due to shock wave and vibration of the building the access hatch leaks and PCV burps through access hatch, now more hydrogen in lower building resulting in explosion 2, same happens again explosion 3 and PCV has lost a lot of pressure and the process stops, looking at the devastation on lower northern side this could work, also watch the video to the north the dust cloud expands more than to the south
why would the valve between reactor 4's suppression pool and the common exhaust stack be open?
 
  • #3,703
Earthmover said:
maybe even build a cofferdam around the whole damn complex like this:

http://youtu.be/2kxVKkXW5Fg


Submerge it inside a giant above ground swimming pool?
 
  • #3,704
Krikkosnack said:
Fuel Rods of the reactor 4... are really those?
http://www.houseoffoust.com/fukushima/rods.html

The limited resolution of the available photos do not make it feasible to 'find' any individual fuel rods.

Perhaps you mean looking for fuel rod _assemblies_.

If I have it right, assemblies would in a BWR -- complete with cladding -- be rather large square sticks, about 4.5 meters long and about 0.14 meter wide -- and that's within the resolution of at least some of these photos. I am not an expert, but I would expect these assembles sticks to be found with a brownish color (unless oxidized, when I think they might form a whitish oxide crust)

For size comparisons some of the roof material scattered everywhere comes handy.
rooftiles4.jpg

The roof 'strips' shown here are from unit 4, and are about 7 m long and about 0.7 m wide. Roof strips from unit 1 and 3 are about the same length, but only half as wide. So good hunting.
 
Last edited by a moderator:
  • #3,705
Dmytry said:
The criticality is not hell on Earth event. In all the mess, it could even be going on somewhere unnoticed. It's not necessary a kaboom, even though it might be a kaboom.

in Tokaimura Criticality Accident
http://www.world-nuclear.org/info/inf37.html
The criticality continued intermittently for about 20 hours. It appears that as the solution boiled vigorously, voids formed and criticality ceased, but as it cooled and voids disappeared, the reaction resumed. The reaction was stopped when cooling water surrounding the precipitation tank was drained away, since this water provided a neutron reflector. Boric acid solution (neutron absorber) was finally was added to the tank to ensure that the contents remained subcritical. These operations exposed 27 workers to some radioactivity. The next task was to install shielding to protect people outside the building from gamma radiation from the fission products in the tank. Neutron radiation had ceased.

"mumble...mumble"
 
  • #3,706
AntonL said:
Lets assume unit 3 pumped unit 4 full of steam and hydrogen...
Hi all,

By the actual status of the release pipes outside the buildings the pipes are broken near unit 3, most likely because of the explosion of unit 3.

But unit 4 exploded later than unit 3. So there was no connection between the two units when unit 4 exploded.

Is it possible that some hydrogen buildup remained in U4 so long from such source? I doubt it.

Otherwise this connection was my favorite idea too.
 
  • #3,707
Is this article correct in that TEPCO could cool the reactors within days if they flooded them with water? Feed and bleed could take months and result in much more widespread radiation release, right?

http://www.bloomberg.com/news/print/2011-04-14/tepco-said-to-estimate-three-months-needed-to-stabilize-fukushima-reactors.html
 
  • #3,708
Dmytry said:
why would the valve between reactor 4's suppression pool and the common exhaust stack be open?

For maintenance and they needed to purge the nitrogen before anyone could enter so it could be open for fresh air purposes.
 
  • #3,709
javadave said:
Is this article correct in that TEPCO could cool the reactors within days if they flooded them with water?

I don't see physics behind the idea. Flooding with water won't help, as water will get heated and evaporate, so there will be a need to constantly add more. It won't be much different from what they do now.

And it won't be shorter, as the problem is not with the heat that is already there - heat is still produced and will be produced for months to come.
 
  • #3,710
Borek said:
I don't see physics behind the idea. Flooding with water won't help, as water will get heated and evaporate, so there will be a need to constantly add more. It won't be much different from what they do now.

And it won't be shorter, as the problem is not with the heat that is already there - heat is still produced and will be produced for months to come.

Thanks. I was wondering what was meant by flooding the reactors with water. I thought that's essentially what they were already doing.
 

Similar threads

Replies
12
Views
48K
Replies
41
Views
4K
Replies
2K
Views
435K
Replies
5
Views
5K
Replies
2
Views
2K
Replies
763
Views
267K
Replies
38
Views
15K
Replies
4
Views
11K
Back
Top