Japan Earthquake: Nuclear Plants at Fukushima Daiichi

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Discussion Overview

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

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested

Main Points Raised

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

Areas of Agreement / Disagreement

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

Contextual Notes

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

  • #271
So according to Reno Denos post things appear to have calmed down at reactors 1-3, am I right in concluding that?

What about the exposed fuel rods in the reactor 4 building? I hear that the water could be completely evaporated ( http://www.nytimes.com/2011/03/17/world/asia/17nuclear.html?_r=1&hp ), something denied by TEPCO though it seems. In case this is true, would it possible that the fuel rods could ignite or melt in some way? Is cooling of these rods in progress?
 
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  • #272
JohanSjoman said:
How come that they did not in some way let the hydrogen gas out of the building before it exploded. Could they not simply make holes in the reactor building?

COULD you? Yes. But that's generally a bad idea, If they KNEW hydrogen was building up they might have, but I'm guessing they had no idea it would explode like it did. In something like this you don't want to do anything to reduce the integrity of the reactor and surrounding structure. Don't want any radioactive materials released of course.
 
  • #273
However, if they had the design (someone said earlier they do) to vent via stacks to the outside, it would seem ridiculous to CHOOSE to vent inside, as the H2 Zr/steam reaction is well known. If it was chosen to vent inside just to allow decay of radiation before emitting outside, you might question the motives behind that choice, no?
 
  • #274
Snippet from BBC:

16 March 2011 Last updated at 16:16 ET
By Richard Black Environment correspondent, BBC NewsReactors

"Once a reactor is turned off, radioactivity and heat generation in the rods die away quickly; down to 7% of the original power within a second of switch-off, 5% within a minute, 0.5% within a day."

If this is true, where is all the heat coming from?
 
  • #275
AntonL said:
radiation leak is a very simple and misleading description

Indeed! It's been frustrating to hear so many TV anchors and reporters speak of "radiation leaks", "radiation exposure", "radiation levels", etc. without bothering to be specific about it.
 
  • #276
Maclomer said:
Snippet from BBC:

16 March 2011 Last updated at 16:16 ET
By Richard Black Environment correspondent, BBC NewsReactors

"Once a reactor is turned off, radioactivity and heat generation in the rods die away quickly; down to 7% of the original power within a second of switch-off, 5% within a minute, 0.5% within a day."

If this is true, where is all the heat coming from?

Let's take unit 2 for example. It is rated at 784 MWe (MegaWatt electric). Let's say that it is 30% efficient, that would mean it is rated at just over 2,600 MWt (MegaWatt thermal). 0.5% of 2,600 is 13 MWt, or 13 million Watts of thermal energy. This is still a considerable amount of energy that needs to be removed via heat transfer.

Ideally water is present, as water is superior to air or steam when it comes to removing heat from an object it comes in contact with. If water is not present, the fuel cannot remove the heat as fast as it produces it, which causes its temperature to rise until it finds equilibrium of heat produced to heat transferred, (energy balance), or it reaches melting point of the material.
 
  • #277
promecheng said:
Let's take unit 2 for example. It is rated at 784 MWe (MegaWatt electric). Let's say that it is 30% efficient, that would mean it is rated at just over 2,600 MWt (MegaWatt thermal). 0.5% of 2,600 is 13 MWt, or 13 million Watts of thermal energy. This is still a considerable amount of energy that needs to be removed via heat transfer.
The heat of vaporization of boiling water is 2260 joules per gram, or 8.55 MJ (megajoules) per gallon. To remove 13 MWt would require boiling about 1.5 gallons of water per second.

Bob S
 
  • #278
Bob S said:
The heat of vaporization of boiling water is 2260 joules per gram, or 8.55 MJ (megajoules) per gallon. To remove 13 MWt would require boiling about 1.5 gallons of water per second.

Bob S

I think that makes sense. I'm rough guessing here as I don't have any tech. specs. in front of me, and no calculator, (sorry for any gross errors). Assuming a 10 ft. diameter x 25' tall vessel, the volume is approximately 15,000 gallons. 1.5 gallons/sec = 5,400 gallons/hr. I think I read earlier on that they thought the RPV would boil down in a few of hours if no water was added. 15,000 / 5,400 = < 3hrs.
 
  • #279
kloptok said:
What about the exposed fuel rods in the reactor 4 building? I hear that the water could be completely evaporated ( http://www.nytimes.com/2011/03/17/world/asia/17nuclear.html?_r=1&hp ), something denied by TEPCO though it seems. In case this is true, would it possible that the fuel rods could ignite or melt in some way? Is cooling of these rods in progress?

This comes from http://news.blogs.cnn.com/2011/03/16/japan-quake-live-blog-death-toll-expected-to-rise-as-crews-reach-more-areas/" , quoting the IAEA

Temperatures recorded at spent fuel pools at the Fukushima plant Tuesday reached 84.0 degrees Celsius (183 Fahrenheit) at Unit 4; 60.4 degrees C (141 F) at Unit 5 and 58.5 degrees C (137 F) at Unit 6, the International Atomic Energy Agency said.

The agency said on Wednesday that "no data" registered for Unit 4, and Unit 5 had risen to 62.7 degrees C (145 F) and Unit 6 had risen to 60.0 degrees C (140 F). The temperature of these pools is normally kept below 25 degrees Celsius (77 degrees F)

"no data"...
 
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  • #280
Here is a link to the original IAEA article.

http://www.iaea.org/newscenter/news/tsunamiupdate01.html

Also,

Injuries or Contamination at Fukushima Daiichi Nuclear Power Plant

Based on a press release from the Japanese Chief Cabinet Secretary dated 16 March 2011, the IAEA can confirm the following information about human injuries or contamination at the Fukushima Daiichi nuclear power plant.

Please note that this list provides a snapshot of the latest information made available to the IAEA by Japanese authorities. Given the fluid situation at the plant, this information is subject to change.

Injuries
2 TEPCO employees have minor injuries
2 subcontractor employees are injured, one person suffered broken legs and one person whose condition is unknown was transported to the hospital
2 people are missing
2 people were ‘suddenly taken ill’
2 TEPCO employees were transported to hospital during the time of donning respiratory protection in the control centre
4 people (2 TEPCO employees, 2 subcontractor employees) sustained minor injuries due to the explosion at unit 1 on 11 March and were transported to the hospital
11 people (4 TEPCO employees, 3 subcontractor employees and 4 Japanese civil defense workers) were injured due to the explosion at unit 3 on 14 March

Radiological Contamination
17 people (9 TEPCO employees, 8 subcontractor employees) suffered from deposition of radioactive material to their faces, but were not taken to the hospital because of low levels of exposure
One worker suffered from significant exposure during ‘vent work,’ and was transported to an offsite center
2 policemen who were exposed to radiation were decontaminated
Firemen who were exposed to radiation are under investigation

The IAEA continues to seek information from Japanese authorities about all aspects of the Fukushima Daiichi nuclear plant.

Taken from the IAEA facebook page.

http://www.facebook.com/notes/inter...uake-update-17-march-0115-utc/202364423126685
 
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  • #281
A couple of speculative questions:
1) Could the "explosion" reported within the #2 containment possibly be similar to a steam hammer event? Rapidly condensing steam vapor in the torus or elsewhere within the containment could have rocked the walls and resulted in a pressure drop. This would not necessarily mean containment was breached.
2) If fuel rods melt or crumble and drop to the bottom of containment or the spent stoage pools, could the fuel mass regain criticality because there would no longer be control rod moderation?
 
  • #282
meadowlark said:
1) Could the "explosion" reported within the #2 containment possibly be similar to a steam hammer event? Rapidly condensing steam vapor in the torus or elsewhere within the containment could have rocked the walls and resulted in a pressure drop. This would not necessarily mean containment was breached.
Gaseous hydrogen mixed with air is a very violent explosive. A hydrogen explosion blew part of the reinforced concrete roof off the experimental area at the Cambridge Electron Accelerator in July 1965. A few liters of spilled liquid hydrogen mixed with the air in the experimental hall, about 30 meters wide by 60 meters long, and was ignited by a spark. One person died, and another seriously injured. See photo in

http://www.sciencemag.org/content/150/3698/866.full.pdf

Bob S
 
  • #283
Astronuc said:
Generally the racks in which spent fuel is stored contain neutron absorbing materials, so if for some reason, the pool was flooded by pure water, the SFP would not go critical. The spent fuel is generally depleted - but each assembly could have some residual positive reactivity, especially as Xe-135 decay. Xe-135 is one of the strongest neutron absorbers, which during operation is in equilibrium - at steady-state, it's production rate = depletion rate.

http://en.wikipedia.org/wiki/Xenon-135

I believe when Unit 4 was shutdown, they did a full-core offload, which means that there is some fuel which still has considerable life left. That would compound the heat burden on the pool, and it would add positive reactivity in the pool.

If TEPCO is concerned, then I'd be concerned too. However, I am not familiar with the practices or their current SFP configuration.

Reactivity is a measure of how a material can contribute to criticality. The multiplication factor, k, is a way to measure criticality. k = 1 means critical (constant power), k < 1 means subcritical (neutrons (neutron flux) and power decreases), and k > 1 means supercritical (neutrons (flux) and power increases).

Positive reactivity increases k, while negative reactivity decreases k.

http://en.wikipedia.org/wiki/Neutron_multiplication_factor

In the spent fuel pool, we want k < 1, always!

http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/u235chn.html#c4
http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/u235chn.html
http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/fiscon.html

See chapter 18 of this book
Nuclear engineering handbook By Kenneth D. Kok
http://books.google.com/books?id=EMy2OyUrqbUC&pg=PA596&lpg=PA596
https://www.amazon.com/dp/1420053906/?tag=pfamazon01-20

Thank you for the response, i'll look up the information you attached shortly.

As a follow up, keep in mind I have no formal training on the material so please excuse my ignorance and I'm sorry if the answers are in the link you provided.
If unit 4 was in shutdown, they did a full-core offload after only one or two cycles and the cells where properly stored within the SFP (subcritical); can you guesstimate (given the fuel used and time since the shutdown) the amount of fuel left in the cells and what the consequences are during the different stages of the coolant failure they are experiencing given that the SFP is outside of the reactor containment unit? What happens when the pool "runs dry" as is now being reported? How fast does the fuel go from subcritical>critical>supercritical? What are the environmental impacts during each stage?
Simple logic tells me that the SFP is totally exposed to the environment given the latest attempts to refill the SFP (their dropping water from helicopters and spraying with water cannons). They started this at roughly 9am their time. This seems like a last ditch effort to me to try and cool the fuel within the SFP and that they are facing a worst case scenario (exposed SFP that is bone dry) yet the radiation levels being reported don't seem to be catastrophic.

Thanks,
Mike
 
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  • #284
promecheng said:
Let's take unit 2 for example. It is rated at 784 MWe (MegaWatt electric). Let's say that it is 30% efficient, that would mean it is rated at just over 2,600 MWt (MegaWatt thermal). 0.5% of 2,600 is 13 MWt, or 13 million Watts of thermal energy. This is still a considerable amount of energy that needs to be removed via heat transfer.

Ideally water is present, as water is superior to air or steam when it comes to removing heat from an object it comes in contact with. If water is not present, the fuel cannot remove the heat as fast as it produces it, which causes its temperature to rise until it finds equilibrium of heat produced to heat transferred, (energy balance), or it reaches melting point of the material.

This might help.
Code:
       BWR  
Unit  Type      Assys   MWt (original)
  1      3       400     1381
  2      4       548     2381
  3      4       548     2381
  4      4       548     2381
  5      4       548     2381
  6      5       764     3293
Based on available data, TEPCO did not uprate those units from the original capacity.
 
  • #285
This question might have been addressed before. I didn't see it though.

What do you (Astronuc and other professions in the Nuclear Power field) believe is the future of the Fukushima Daiichi units that are affected by this incident?

Such as do you believe they will be decommissioned? Or repaired for future operation?
 
  • #286
promecheng said:
I think that makes sense. I'm rough guessing here as I don't have any tech. specs. in front of me, and no calculator, (sorry for any gross errors). Assuming a 10 ft. diameter x 25' tall vessel, the volume is approximately 15,000 gallons. 1.5 gallons/sec = 5,400 gallons/hr. I think I read earlier on that they thought the RPV would boil down in a few of hours if no water was added. 15,000 / 5,400 = < 3hrs.

This article from the Union of Concerned Scientists explains the boild off rate well.http://allthingsnuclear.org/post/3859682324"
 
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  • #287
What do you (Astronuc and other professions in the Nuclear Power field) believe is the future of the Fukushima Daiichi units that are affected by this incident?

This has been answered too. The seawater+boric acid combo used to cool 1-3 has essentially eliminated any chance for their future use. 4-6 are anyone's guess though.
 
  • #288
bondboy said:
Thank you for the response, i'll look up the information you attached shortly.

As a follow up, keep in mind I have no formal training on the material so please excuse my ignorance and I'm sorry if the answers are in the link you provided.
If unit 4 was in shutdown, they did a full-core offload after only one or two cycles and the cells where properly stored within the SFP (subcritical); can you guesstimate (given the fuel used and time since the shutdown) the amount of fuel left in the cells and what the consequences are during the different stages of the coolant failure they are experiencing given that the SFP is outside of the reactor containment unit? What happens when the pool "runs dry" as is now being reported? How fast does the fuel go from subcritical>critical>supercritical? What are the environmental impacts during each stage?
Simple logic tells me that the SFP is totally exposed to the environment given the latest attempts to refill the SFP (their dropping water from helicopters and spraying with water cannons). They started this at roughly 9am their time. This seems like a last ditch effort to me to try and cool the fuel within the SFP and that they are facing a worst case scenario (exposed SFP that is bone dry) yet the radiation levels being reported don't seem to be catastrophic.

Thanks,
Mike
We will hopefully get the technical details for the fuel and SFP.

The fuel assemblies have some positive reactivity based on their enrichment, burnup and configuration. However, it's the combination of the spent fuel racks (which contain a neutron absorber) and the fuel. I would expect that the fuel offload includes once-burned fuel, twice-burned, and I would guess some thrice-burned for discharge. I'll have to do some basic guesstimates, but I'd really need batch sizes.
 
  • #289
Angry Citizen said:
This has been answered too. The seawater+boric acid combo used to cool 1-3 has essentially eliminated any chance for their future use. 4-6 are anyone's guess though.

Thank you
 
  • #290
crazyisraelie said:
This question might have been addressed before. I didn't see it though.

What do you (Astronuc and other professions in the Nuclear Power field) believe is the future of the Fukushima Daiichi units that are affected by this incident?

Such as do you believe they will be decommissioned? Or repaired for future operation?
Boiling saltwater in SS304 is not a good idea. Basically, I expect those units are history. The fuel and control rods in Unit 1, 2 and 3, are likely damaged, and therefore waste. The stainless steel internals and control rod drive systems are likely compromised. They will have to be decontaminated, and then disposed of properly.

The other big question is the contamination around and in the units that could preclude any meaningful recovery work.

Those units could be mothballed for years, and at some point there will be a big decomissioning project.
 
  • #291
I think a better question is then,

Do you think the plant site could be reused for future reactors?
 
  • #292
crazyisraelie said:
I think a better question is then,

Do you think the plant site could be reused for future reactors?
We shall see.

There were plans for Unit 7 and 8, both being ABWRs. I suspect those plans are suspended indefinitely until the current crisis is resolved.

TEPCO has probably lost credibility with the government and public. The release of fission products to the environment has violated the obligation to the protect the public from exposure to radiation. The sacred trust is broken.
 
  • #293
Astronuc said:
We shall see.

There were plans for Unit 7 and 8, both being ABWRs. I suspect those plans are suspended indefinitely until the current crisis is resolved.

Again thank you for your information. It's just concerning seeing how this might kill the progress we are making in the states towards a nuclear revival.
 
  • #294
crazyisraelie said:
Again thank you for your information. It's just concerning seeing how this might kill the progress we are making in the states towards a nuclear revival.
It certainly makes it more difficult.
 
  • #295
crazyisraelie said:
I think a better question is then,

Do you think the plant site could be reused for future reactors?
There are still lots of facilities and equipment at that site, even if the reactors are toast and are entombed or monitored until they can be dismantled.

There is a strong rejection of any coal-based power here in Maine - especially along the coast where tourism is king. Still, after Maine Yankee was decommissioned, there were plans floated (one just ~2-3 years ago) to establish a coal-fired power plant in Wiscassett and use as much of the Maine Yankee infrastructure as possible.

Given the recent history of that installation, I'd personally offer low odds on any new reactors on that site. And hauling coal to Japan is not going to be cheap.
 
  • #296
turbo-1 said:
Given the recent history of that installation, I'd personally offer low odds on any new reactors on that site. And hauling coal to Japan is not going to be cheap.
Looks like Japan will be getting Siberian coal, LNG, and maybe even electricity from Russia, according to Prime Minister Dmitry Medvedev:

"Our moral duty is to help [Japan] in this situation," Mr. Medvedev said Monday as he ordered Deputy Prime Minister Igor Sechin to look into ways of redirecting up to 6,000 megawatts of electrical power from Russia's far east, and arrange delivery of an additional 200,000 tons of liquified natural gas (LNG) plus unspecified amounts of Siberian coal over the next two months.

See http://www.csmonitor.com/World/Europe/2011/0315/Japan-gets-coal-gas-from-historic-rival-Russia

Bob S
 
  • #297
thats really helpful coming from a country like russia who generally are well known for keeping to themselves
 
  • #298
promecheng said:
Let's take unit 2 for example. It is rated at 784 MWe (MegaWatt electric). Let's say that it is 30% efficient, that would mean it is rated at just over 2,600 MWt (MegaWatt thermal). 0.5% of 2,600 is 13 MWt, or 13 million Watts of thermal energy. This is still a considerable amount of energy that needs to be removed via heat transfer.

Ideally water is present, as water is superior to air or steam when it comes to removing heat from an object it comes in contact with. If water is not present, the fuel cannot remove the heat as fast as it produces it, which causes its temperature to rise until it finds equilibrium of heat produced to heat transferred, (energy balance), or it reaches melting point of the material.

Promecheng - Thanks for the good answer - taking the BBC figures, the rate of decay is extremely fast in the beginning and then it slows down - I assume because it is the sum of several exponentials. Given that it is .5% at the end of Day 1, I therefore assume it will still be a significant number at Day 6; using your numbers and a guess I suppose we can't count on a decline of significant heat production for quite a few days yet?
 
  • #299
The Japanese have started operations to re-fill the spent fueling pools. Radiation levels over the pools at 1000ft are in the milliSv/hr range.

I'm beginning to wonder though if this is unnecessary: The spent fuel shouldn't be able to get hot enough to cause any damage - certainly not enough to melt.

Vanadium melts at 2183K
The fuel is cladded and encased in neutron absorbing substances.

Even if we assumed that they had a 50cm cubic block of material in one place, and radiation was the only means of balancing the heat produced, the equilibrium temperatures shouldn't be anywhere near that:

Back of the envelope calcs:
50cm cubic block of spent fuel, 40 days old

LaMarsh, pg 415 suggests a rough exponential relationship for the power ratio in fuel over infinite cooldown time: y = 1.0023E-02exp(-2.3049E-07*x) y is power ratio, x is seconds



0.5 emissivity (pulled out of ***)

reactor operating at 50W/cm^3 initially, 0.225 W/cm^3 in fuel after 40 days.

Equilibrium temp: 900K

That's hot, but I don't see how it is hot enough to do anything other than light fuel oil on fire. It shouldn't be enough to melt the cladding. NEI is of the opinion that vanadium fires are impossible to start, requiring even higher temperatures than melting down the vanadium.


I have to wonder if people aren't risking their lives right now due to an overreaction. If these calcs produce anything resembling reality, they should probably just leave it sit.
 
  • #300
Sorry, can't immediately quote the reference, but in addition to the spent fuel rod assemblies in the SFP at unit 4 there were "Hot" fuel rod assemblies taken from the core when they shut down the reactor for maintenance in 2010.

I also read somewhere that the helicopter water drop tried initially was aborted perhaps because the roof was still covering the SFP at unit 4.

Again, I post this picture with my personal interpretation of what I am seeing at unit 4. I now notice a subtle, but definite faint cloud of darker, sooty smoke coming from the square hole or perhaps the ground below, and rising diagonally across the tower at the right. And if there is still water, boiling, then where is the steam? And if not, could it get hot enough to crumble concrete, melt structural steel, and start secondary fires in things like the oil in the generators? What else might cause a square hole in the side of the building with smoke coming out of it? Inquiring minds want to know.

r735227_5964756.jpg


all is not well at unit 4, IMO
 
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