Japan Earthquake: Nuclear Plants at Fukushima Daiichi

Click For Summary
The Fukushima Daiichi nuclear plant is facing significant challenges following the earthquake, with reports indicating that reactor pressure has reached dangerous levels, potentially 2.1 times capacity. TEPCO has lost control of pressure at a second unit, raising concerns about safety and management accountability. The reactor is currently off but continues to produce decay heat, necessitating cooling to prevent a meltdown. There are conflicting reports about an explosion, with indications that it may have originated from a buildup of hydrogen around the containment vessel. The situation remains serious, and TEPCO plans to flood the containment vessel with seawater as a cooling measure.
  • #751
Fukushima Daiichi nuclear power plant near the sea damaged by the earthquake east, found that the concentration of radioactive material falls up to 126 times the safety standards, announced at a press conference early Tuesday TEPCO 22.

According to TEPCO, near the outlet 21 at 2:30 pm were examined with 0.5 liters of water collected, the criteria established by the Nuclear Reactor Regulation Law is 126.7 times the iodine 131 was detected. This water year, and continue to take every day, the annual limit public exposure to radiation falls on 126.7-fold (nuked) will be. Cesium 134 is a standard 24.8-fold addition, the cesium-137 detected 16.5-fold

http://translate.google.com/translate?sl=ja&tl=en&js=n&prev=_t&hl=da&ie=UTF-8&layout=2&eotf=1&u=http%3A%2F%2Fwww.asahi.com%2Fnational%2Fupdate%2F0322%2FTKY201103210384.html
 
Engineering news on Phys.org
  • #752
Reno Deano said:
One note: 5.9 milliBq/cm3 is not over any limit. Even if it was 5.9KBq/cm3 it would be be the Occupational DAC (10 CFR 20, Appendix B) limit of 7.4E3 Bq/cm3. Hope my conversions are correct!

No, those would be horrible levels. http://www.nrc.gov/reading-rm/doc-collections/cfr/part020/appb/Iodine-131.html" says that the inhalation DAC for I-131 is 2E-8 microcurie per ml, which is 0.74 milliBq/cm3.
 
Last edited by a moderator:
  • #753
Hi. In this video at about 4:19 in my opinion has fuel rods
Look at the shape of those, looks just like these
AntonL said:
04710042klein.jpg

What you think?

edit: It seems this video was here already. Just missed it because screen caps are not visible anymore due to exceeded bandwith.. :|
 
Last edited by a moderator:
  • #754
HansHooligan said:
Hi. In this video at about 4:19 in my opinion has fuel rods
Look at the shape of those, looks just like these

What you think?

edit: It seems this video was here already. Just missed it because screen caps are not visible anymore due to exceeded bandwith.. :|


When looking at the video you can quite clearly see the so called fuel rods extending out from concrete slabs at steady intervals. That is rebar, not fuel rods.

Also if you look at the IR shots from today you see no heat signature from where these so called fuel rods are. If these were real fuel rods they would be warmer than ambient.
 
Last edited by a moderator:
  • #755
I missed that "at steady intervals", seems more like "just a bunch of sticks".
I don't think that those thermal images are accurate enough to show 10mm thick fuel rods unless those are at really high temperature.

Just my 2 cents.
 
  • #756
HansHooligan said:
I missed that "at steady intervals", seems more like "just a bunch of sticks".
I don't think that those thermal images are accurate enough to show 10mm thick fuel rods unless those are at really high temperature.

Just my 2 cents.

With THAT many fuel rods close together they would show. The only "proof" there is of those being fuel rods is a layman's opinion after looking at some shaky, low resolution and blurry footage. Also real fuel rods are bunched together in bundles. If they were fuel rods, how could all of the fuel rods be completely detached from their bundles and still staying that intact as in the video? And have no of the bundle parts attached to them?

And on top of that we also have the IR images showing NO heat from that area. Keep in mind thermal imaging resolution does not work the same way as resolution in a regular camera. Heat coming from a 1cm thick rod will not require a 1cm/pixel resolution of the camera since heat radiates and heats up stuff around the object producing heat.

IF they are fuel rods I will eat my hat.
 
  • #757
Maxion said:
When looking at the video you can quite clearly see the so called fuel rods extending out from concrete slabs at steady intervals. That is rebar, not fuel rods.

Also if you look at the IR shots from today you see no heat signature from where these so called fuel rods are. If these were real fuel rods they would be warmer than ambient.

I don't know if these are fuel rods or some other rod. I don't know the exact relationship of the location of the "rods" to the heat signatures seen on the IR photos posted today. I do know that after the explosion, in this pile of rubble, in this field of view, it would be somewhat reassuring to see even one bent piece of a rod. Absent that, one possible conclusion is that these rods seem to be much more rigid than the bent rebar seen in other areas. If any of these were once embedded in concrete, I can see no conclusive evidence of it on this shot.

I also believe that the green structure in the lower right may be part of the fuel rod handling equipment. If so, then it might support the notion that these are at least somewhere near the location of the SFP.

I also believe the reports that some high level radioactive debris are on the ground and that they have sufficient activity, if not obvious heat, to warrant the workers using dozer blades attached to military tanks to clear the high-level radioactive debris to permit safer access to work on units 3 & 4. There aren't that many different possibilities of sources for high-level radioactive debris on the ground that I can think of.

I suspect I can no more convince anyone these are fuel rods than anyone can convince me that after the explosion, all the fuel rods are still in the SFP and that they survived the blast, unscathed.
 

Attachments

  • Screen shot 2011-03-21 at 6.04.jpg
    Screen shot 2011-03-21 at 6.04.jpg
    30.2 KB · Views: 541
Last edited:
  • #758
The JPG picture T-cup shows doesn't look like re bar to me. RE bar would bend. There are other pictures of bend re bar in other clips. These sure look like a pile of fuel rods like in #757. None of it is bent and I don't see any attached concrete
 
  • #759
|Fred said:
@Wombat
Well if I'm not mistaken in your calculation you assume that the radiation level measure taken at x meters are "induce" from the radiation source hence your reverse invert square law calculation.

In my opinion you are likely making a false assumption / interpretation : The radiation source are more likely the volatile isotope in the air , at least for the most part.


ps: to make my self more understandable your calculation would be right if let say you had a pile of radioactive isotope outside your windows, you were in your house and wanted to know how radioactive this pile was taking a measurement from a distance. But what we have here is a window leaking and wind blowing some of the stuff to the inside..

Thanks for your comment Fred,

The origin of this line of reasoning was the the possibility that the lava-like discharge from the hole in the north side of reactor 4 is corium. Corium would emit gamma rays.

See:
https://www.physicsforums.com/showpost.php?p=3193343&postcount=331
https://www.physicsforums.com/showpost.php?p=3194084&postcount=381
https://www.physicsforums.com/showpost.php?p=3195114&postcount=416

I have no way of ruling out lofted radio-nucleotides as the source of the radiation.
 
  • #760
Here are a few questions for those more sure than me to ponder:

What is a reasonable estimate of the mean age of spent fuel rods stored in a SFP after removal from the reactor? Is it possible that after many months or years in the SFP the rods might have exhausted the residual heat to level that they would not glow and might be lost in the background heat signature coming from the ruins of Unit 3?

What might become of the contents of one of those casks coming off or going back on one of the two refueling flatbed trucks seen out back of unit 3 in the satellite photos?

Are shiney, "new" low level enriched uranium (oxide?) fuel rods that have not been in a reactor extremely hot before the fission reaction has occurred in the core of a reactor?

If a fuel rod cask were being downloaded or uploaded, what would the actual process be? Might there be some point in the re-fueling or de-fueling process where the rods would be out of the racks and perhaps in a state or location more vulnerable to a disastrous accident like the current chain of events?

How robust are the racks and individual rod bundles that hold together a fuel rod assembly.

How robust are the casks in which fuel rod assemblies are transported?

If the fuel rods are spent (with respect to the level of fissionable materials present necessary to sustain an efficient chain reaction in the core), then would it be reasonable to suspect loosely scattered rods such as these pictured, if they were spent, would necessarily heat up more in their haphazard arrangement?

I don't know the answer to any of these questions.
 
  • #761
TCups said:
Here are a few questions for those more sure than me to ponder:

What is a reasonable estimate of the mean age of spent fuel rods stored in a SFP after removal from the reactor? Is it possible that after many months or years in the SFP the rods might have exhausted the residual heat to level that they would not glow and might be lost in the background heat signature coming from the ruins of Unit 3?

What might become of the contents of one of those casks coming off or going back on one of the two refueling flatbed trucks seen out back of unit 3 in the satellite photos?

Are shiney, "new" low level enriched uranium (oxide?) fuel rods that have not been in a reactor extremely hot before the fission reaction has occurred in the core of a reactor?

If a fuel rod cask were being downloaded or uploaded, what would the actual process be? Might there be some point in the re-fueling or de-fueling process where the rods would be out of the racks and perhaps in a state or location more vulnerable to a disastrous accident like the current chain of events?

How robust are the racks and individual rod bundles that hold together a fuel rod assembly.

How robust are the casks in which fuel rod assemblies are transported?

If the fuel rods are spent (with respect to the level of fissionable materials present necessary to sustain an efficient chain reaction in the core), then would it be reasonable to suspect loosely scattered rods such as these pictured, if they were spent, would necessarily heat up more in their haphazard arrangement?

I don't know the answer to any of these questions.

TCups,

All very good, well organized, clearly stated questions... simple answer... where is Astronuc !

Rhody... :bugeye:
 
  • #762
rhody said:
TCups,

All very good, well organized, clearly stated questions... simple answer... where is Astronuc !

Rhody... :bugeye:

On his way to Japan? He said that was his immediate goal if he could get there.
 
  • #763
cask integrity:

I don't know about modern ones, but back when I was going to nuke school, it was noted that they were designed to drop, burning from a truck on an overpass into the path of a train and not be compromised.

They are supposed to be pretty tough things.
 
  • #764
TCups said:
On his way to Japan? He said that was his immediate goal if he could get there.

TCups,

To the best of my knowledge as of Sunday evening no, he said it would be some time before he may travel there. We could use his expertise since it revolves around the aging process of the fuel and fuel mixtures used. I am sure if he is about he will pop in and contribute.

Just to lighten the mood somewhat, don't you guys, TCups, AtomicWombat, etc... ever sleep ! Sometimes to step away for a bit allows your brain to mull things over and you come back with fresh insight. It happens for me once in awhile, mostly in the shower in the early am.

When this whole affair wraps up, hopefully positively, I hope you guys stick around and contribute your life skills, it has been interesting to watch to say the least.

Rhody... :wink:
 
  • #765
TCups said:
Here are a few questions for those more sure than me to ponder:

What is a reasonable estimate of the mean age of spent fuel rods stored in a SFP after removal from the reactor? Is it possible that after many months or years in the SFP the rods might have exhausted the residual heat to level that they would not glow and might be lost in the background heat signature coming from the ruins of Unit 3?

Mean age? probably 10 to 20 years. They would certainly not be 'glowing' hot.

What might become of the contents of one of those casks coming off or going back on one of the two refueling flatbed trucks seen out back of unit 3 in the satellite photos?
I expect they’re putting fuel into dry storage casks, though I really don’t know.

Are shiney, "new" low level enriched uranium (oxide?) fuel rods that have not been in a reactor extremely hot before the fission reaction has occurred in the core of a reactor?
The new fuel isn’t even warm to the touch. You could safely keep it in your kitchen.

If a fuel rod cask were being downloaded or uploaded, what would the actual process be? Might there be some point in the re-fueling or de-fueling process where the rods would be out of the racks and perhaps in a state or location more vulnerable to a disastrous accident like the current chain of events?
Not sure what you mean here. I don’t think the rods are pulled from the assemblies at any time.

How robust are the racks and individual rod bundles that hold together a fuel rod assembly.
They are very robust. If you dropped an assembly from the crane you might bend the first row.

How robust are the casks in which fuel rod assemblies are transported?
Here in the US they are extremely robust. Google for videos of the casks being hit by locomotive at high speed, etc.

If the fuel rods are spent (with respect to the level of fissionable materials present necessary to sustain an efficient chain reaction in the core), then would it be reasonable to suspect loosely scattered rods such as these pictured, if they were spent, would necessarily heat up more in their haphazard arrangement?
No, the arrangement doesn’t alter the heat generated in any given rod; the heat is just the fission products decaying away at their given rate.

I'm not a BWR guy so these are just my best guess answers. Hope that helps.
 
  • #766
Aside:
OK, I bit the bullet and spent $2.99 (not auto renewing) and paid by PayPal so I have unlimited bandwidth for the next 30 days. The links in the previous posts should be working once more. Now I am even more "invested" I suppose.
 
  • #767
gmax137 said:
Mean age? probably 10 to 20 years. They would certainly not be 'glowing' hot.I expect they’re putting fuel into dry storage casks, though I really don’t know.The new fuel isn’t even warm to the touch. You could safely keep it in your kitchen.Not sure what you mean here. I don’t think the rods are pulled from the assemblies at any time.They are very robust. If you dropped an assembly from the crane you might bend the first row.Here in the US they are extremely robust. Google for videos of the casks being hit by locomotive at high speed, etc.No, the arrangement doesn’t alter the heat generated in any given rod; the heat is just the fission products decaying away at their given rate.

I'm not a BWR guy so these are just my best guess answers. Hope that helps.

OK, so it would not be reasonable to expect a sideways blast into the SFP could "disassemble" a fuel rod assembly, I suppose. Probably not even with a shock wave traveling through water rather than air. But it seems possible, in the unlikely event that these are fuel rods, that they might not have a high heat signature in the IR range. Now we need some x-ray imagery of the site, I suppose.

The question of the origin of the unbent rods remains unanswered.
 
  • #768
AntonL said:
First IR image released in news broadcast
Heat.jpg


Hot spot over spent fuel pools indicated as 128 deg C and multiple hot spots at other places
(at the moment I cannot listen to the broadcast - only watch so no idea what they saying

Well 128 C means the SFP (assuming that is what it is) is definitely not covered with water (at atmospheric pressure) at the time of the IR photo. Steam at atmospheric pressure will usually only be at 100 C. So whatever is being viewed is solid or the solid crust of a molten mass.

Can anyone direct me to the original source of these IR images?
 
  • #769
TCups said:
I tried last evening, for a good hour, to confirm from any independent source, the exact layout of the floor plans of any of the units at Fukushima.

Picture7-1.png


Does anyone have a better source for the actual "anatomy" of what the Fukishima facility is supposed to be, rather than a stylized schematic? A blueprint or floor plan would certainly help to be able to draw more informed conclusions about what is seen.
Thanks.

TCups,
I think you can safely assume that the SFP and equipment pool straddle either side of the reactor on the long orientation of the reactor building (i.e the 45 m length). The large crane spans the 35 metre dimension of the building. So the SFP and equipment pool will be approximately centred on the north and south walls of each reactor building, or perhaps slightly offset from the centre line.

I think you are basically correct. The hole just above the steam is the SFP. The steam in the image comes from roughly from the "cattle run" between the reactor and the SFP. The hole to the right, with the "cut-out" of the steel frame above it, is the reactor plug hole.
 
  • #770
TCups said:
Here are a few questions for those more sure than me to ponder:

What is a reasonable estimate of the mean age of spent fuel rods stored in a SFP after removal from the reactor? Is it possible that after many months or years in the SFP the rods might have exhausted the residual heat to level that they would not glow and might be lost in the background heat signature coming from the ruins of Unit 3?

At one time before moving "old" spent fuel from the SFP to Dry Casks, the age could have been 10 years or more. Due to the 2/3 burn-up the long lived fission products (Cs-137, PU, etc, would give then a good heat signature.

What might become of the contents of one of those casks coming off or going back on one of the two refueling flatbed trucks seen out back of unit 3 in the satellite photos?

Coming off the truck they would be empty. Going on they would be full and destined for fuel reprocessing in France

Are shiney, "new" low level enriched uranium (oxide?) fuel rods that have not been in a reactor extremely hot before the fission reaction has occurred in the core of a reactor?

HE fuel bundles (navy type is room temperature.) LE Fuel bundles is less than room temperature, and individual rods are ambient temperature.

If a fuel rod cask were being downloaded or uploaded, what would the actual process be? Might there be some point in the re-fueling or de-fueling process where the rods would be out of the racks and perhaps in a state or location more vulnerable to a disastrous accident like the current chain of events?

Spent fuel bundles/modules are either loaded into casks under water or by a shielded transfer container. Pieces of rods are keep out of the casks.

How robust are the racks and individual rod bundles that hold together a fuel rod assembly.

Robust enough to withstand high pressure oscillations with within the core and incidents normal to transportation. The SFP racks are designed with seismic considerations.

How robust are the casks in which fuel rod assemblies are transported?

Almost indestructible. Goggle: DOE Spent Fuel Shipping Cask Testing

If the fuel rods are spent (with respect to the level of fissionable materials present necessary to sustain an efficient chain reaction in the core), then would it be reasonable to suspect loosely scattered rods such as these pictured, if they were spent, would necessarily heat up more in their haphazard arrangement?

The picture is from a fuel manufacturing facility, prior to them being placed into the fuel bundle matrix/array. Spent fuel rods from power reactors would be oxidized and not sparkling.
I don't know the answer to any of these questions.

See italicised answers below your questions.
 
Last edited:
  • #771
IR for reactor 3 -- I believe this indicates 62 C over the fuel pool, 128 C on the other side of the reactor head:
| http://www.welt.de/multimedia/archive/01340/Fukushima_hoch_DW__1340857z.jpg

Interesting picture here -- I do not believe the crane and cars are at reactor ground level, but rather on the embankment behind the reactors:
| http://tvde.web.infoseek.co.jp/cgi-bin/jlab-dat/s/795434.jpg

Detailed ground level radioactivity readings (I do not know where this picture comes from nor its reliability, but it appears to be genuine):
| http://static.ow.ly/photos/original/9ooW.jpg
The highest readings are just to the west and north of reactor 3. These reading may be consistent with the French agency's conclusion (and, I believe, an early conjecture here in this thread) that the protection shield over the reactor has disappeared. Gamma ray radiation could then be reflected back down around the reactor building by the remaining beams and detritus (as well as simply backscattered by the atmosphere).
| http://www.irsn.fr/FR/Actualites_pr...Seisme-Japon_Point-situation-20032011-06h.pdf
The annotated photo in this French IRSN report interprets the north side of reactor 3 as being the ruins of the destroyed service deck as well as the floor beneath the service deck.

Here is some preliminary evidence from the Test Ban Treaty Organisation that there has been no major destruction of the zirconium cladding:
| http://www.nature.com/news/2011/110317/full/news.2011.168.html
" ... the data show high amounts of volatile radioactive isotopes, such as iodine and caesium, as well the noble gas xenon. But so far, the data show no high levels of the less volatile elements such as zirconium and barium that would signal that a large meltdown had taken place ... "
 
  • #772
rhody said:
TCups,

To the best of my knowledge as of Sunday evening no, he said it would be some time before he may travel there. We could use his expertise since it revolves around the aging process of the fuel and fuel mixtures used. I am sure if he is about he will pop in and contribute.

Just to lighten the mood somewhat, don't you guys, TCups, AtomicWombat, etc... ever sleep ! Sometimes to step away for a bit allows your brain to mull things over and you come back with fresh insight. It happens for me once in awhile, mostly in the shower in the early am.

When this whole affair wraps up, hopefully positively, I hope you guys stick around and contribute your life skills, it has been interesting to watch to say the least.

Rhody... :wink:

(deep sigh) - I work all day in front of 6 large computer screens and 3 computers (one is a Mac) interpreting images of women's breasts. Go figure. A physician by occupation, I gave up getting sleep on any regular basis years ago. Looking at exploding reactors is a pleasant diversion, weird as that seems. And I enjoy the exchange here. I have learned a lot.
 
  • #773
Astro is headed to the West Coast office of his employer. He said during chat that his presence here would by sporadic for a while. And yes, he does want to be able to travel to Japan as a consultant/troubleshooter.
 
  • #774
Some BOTE calculations of the pressure impulse required to lift the concrete shield plug 500 metres into the air (assuming this is what occurred in the reactor 3 explosion).

Width of plu ~ 10 metres.
Thickness ~ 2 m
Density ~ 2.5 tonnes/m^3
Weight = pi*5^2*2 ~ 400 tonnes
Area ~ pi*5^2 = 80 m^2

Energy required to lift 400 t to 500 metres = mgh = 400000*10*500 = 2*10^9 J = 2000 MJ

impulse is force*delta_t = 2000 MJ assuming no loss
Pressure Impulse = Impulse/area => 2000*10^6/80 = 2.5*10^7 = 25 *10^6 Pa = 25 MPa = 250*delta_t atm.Assume delta_t = 1 sec, Pressure is 250 atm.

Primary containment is rated to about 500 kPa (5 atm) - will present no barrier to this pressure impulse.

Reactor pressure vessel has a design pressure of 1250 psig ~ 85 atm. Assuming 100% overdesign this is 170 atm.

http://img863.imageshack.us/img863/3206/reactor.jpg

The pressure transient required to blast the concrete plug to 500 metres is of the order required to rupture the reactor - assuming the reactor was not breached by a melt-down in the first place.
 
Last edited by a moderator:
  • #775
AtomicWombat said:
Some BOTE calculations of the pressure impulse required to lift the concrete shield plug 500 metres into the air (assuming this is what occurred in the reactor 3 explosion).

The pressure transient required to blast the concrete plug to 500 metres is of the order required to rupture the reactor - assuming the reactor was not breached by a melt-down in the first place.
Maybe not! Sometimes if you just keep looking, you will see the obvious. . .

1) the north wall did not collapse inward. The vertical and diagonal overlay pattern of the roof beams is the normal structure of the roof beams. Compare the intact beam structure of Unit 4 to the undamaged remaining portions of Unit 3.

2) The central portion of Unit 3's roof beams are intact, and, I believe, collapsed downward after the initial blast blew out the south wall and the crane blew back through the north wall. This hint actually came from the French-annotated picture, above, fuzefiz's post. The heavy overhead crane structure was blasted out the back wall, falling on and heavily damaging a portion of the building below (arrow)

3) Implication: the plug is likely still atop the core containment, roughly in the center third of the damaged Unit 3 bldg. The blast came outward through the SFP gate, breeching the side of the containment, then, upward, out of the SFP (circle).

4) The sidewise blast peeled back a part of the corner of Unit 4.

Picture30-2.jpg


Again, this:
Oyster-Creek-reactor.gif
 
Last edited:
  • #776
"The pressure transient required to blast the concrete plug to 500 metres is of the order required to rupture the reactor - assuming the reactor was not breached by a melt-down in the first place."

Quite apart from your calculations and the correctness of the assumptions, the effect is either or, not both. The energy necessary to blast the "cork" would rupture and destroy the containment first, thereby dispersing the energy that would have been required to shoot the lid in the air.

If there were dimensions to calculate the volume of the containment it would be possible to see whether that volume (given the pressure and likely mixture characteristics) would in fact contain enough explosive energy.

My guess is that the theory of path of least resistance through the gate to the SFP is the most likely scenario.
 
  • #777
"Implication: the plug is likely still atop the core containment. The blast came outward through the SFP gate, breeching the side of the containment, then, upward, out of the SFP."

Only problem is that that doesn't mash with the actual lay out, where the SFP is on the other side of the building (South side). What appears to have been blasted away in that photograph would be the equipment pool, which in the schematics appears much less heavy duty than the SFP anyway. (Not surprising as it is less deep, smaller and does not contain tons of fuel rods in addition to water. The schematics are not clear about there being a gate between the equipment pool and the containment head, probably not as what goes in the equipment pool is not as active as fuel assemblies.
 
  • #778
UCS details on SFPs:

http://allthingsnuclear.org/post/4008511524/more-on-spent-fuel-pools-at-fukushima"
 
Last edited by a moderator:
  • #779
Bez999 said:
"The pressure transient required to blast the concrete plug to 500 metres is of the order required to rupture the reactor - assuming the reactor was not breached by a melt-down in the first place."

Quite apart from your calculations and the correctness of the assumptions, the effect is either or, not both. The energy necessary to blast the "cork" would rupture and destroy the containment first, thereby dispersing the energy that would have been required to shoot the lid in the air.

Well, no. A pressure vessel in the primary containment would have to withstand a pressure transient that blew that containment apart.

Bez999 said:
My guess is that the theory of path of least resistance through the gate to the SFP is the most likely scenario.

It is not clear to me that the gate to the SFP forms part of the primary containment wall. It seems to be the drywell head and removable shield plugs form a barrier to the SFP when the reactor is operating. These are removed during refueling.
 
  • #780
AtomicWombat said:
UCS details on SFPs:

http://allthingsnuclear.org/post/4008511524/more-on-spent-fuel-pools-at-fukushima"

tumblr_lifbzqVHKZ1qbnrqd.jpg


According to this table the heat generation from unit 4 SFP is 1,600 * 1000 kcal/hr.

This is 1,600 * 1000 *4.2/3600 kW = 1867 kW ~ 2 MW.

My earlier estimate of 8 MW was a factor of 4 too high:
http://74.86.200.109/showpost.php?p=3192958&postcount=302"
 
Last edited by a moderator:

Similar threads

  • · Replies 12 ·
Replies
12
Views
49K
  • · Replies 41 ·
2
Replies
41
Views
5K
  • · Replies 2K ·
60
Replies
2K
Views
451K
  • · Replies 5 ·
Replies
5
Views
6K
  • · Replies 2 ·
Replies
2
Views
2K
  • · Replies 6 ·
Replies
6
Views
20K
  • · Replies 763 ·
26
Replies
763
Views
274K
  • · Replies 38 ·
2
Replies
38
Views
16K
Replies
6
Views
4K
  • · Replies 4 ·
Replies
4
Views
11K