I am currently compiling an update for the Fukishima Nuclear Accident as of March 17. The situation is developing very quickly and commenters on this thread (March 16 updates) are doing an excellent job at posting regular updates.
Meanwhile, here is a guest post from Luke Weston.
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Looks like we need an update post on the situation with the Fukushima nuclear power reactors. The situation continues to change and develop, but good, sensible, detailed information is still hard to find.
In the wake of the Fukushima incident, it has really helped me to understand what happened in 1979 at Three Mile Island; with nonsense all throughout the media, and FUD, and panic spreading, with good information almost impossible to find, and with the over-abundance of bad information leading to hysteria.
But this is the first time it has happened to the Facebook and Twitter generation; I’ve yet to determine whether that’s a good thing or a bad thing. We need to keep working hard to make sure it’s a net benefit for the good information, not the dodgy information.
Design Basis Godzilla
Why wasn’t the earthquake design basis set high enough?, some people ask. What if the next earthquake is magnitude 10? Magnitude 12? Magnitude 20? But where does it stop? Where do you set the design basis? What if the reactor is attacked by Godzilla?
No matter where you set the design basis, you will always exceed it one day, eventually. And when you do, the anti-nuclearists will complain that the design basis is not set high enough.
There is always some really extreme, really catastrophic situation that you can imagine, but what is its probability in any given year?
It’s all about Probabilistic Risk Assessment.
You know what the average probability per year of a magnitude 8 earthquake in the area is, what the probability of a magnitude 9 earthquake is, what the probability of a large tsunami is, etc. I’m not sure what the probability of Godzilla attack is. Need to ask an expert. Somebody get Matthew Broderick in here; he’s the guy to ask.
And you decide what the acceptable probability of a severe core damage (“meltdown”) incident (which won’t hurt anybody but will probably write off the reactor, like TMI) for the nuclear reactor is in any given year – let’s suppose it is decided that one such failure per 50,000 reactor-years of operation is acceptable. Then, with that in mind, you design the degree of seismic hardening and safety engineering for the nuclear power plant so that you hit that target.
It is the safest way to do it which is actually realistic. You can’t say that it’s absolutely 100% resistant to any hypothetical scenario of destruction that you can imagine, because there is always something that you can imagine that is more destructive.
Seawater injection into the primary containment of Unit 1 – not into the reactor vessel itself
On 12 March, TEPCO announced that they planned to cool the Unit 1 reactor with seawater, adding boric acid to the water as a nuclear poison, to prevent any possibility of unintended criticality. The injection of fresh water and seawater into the primary containment vessel through a fire-extinguishing system line commenced on the 13th of March.
This is not an injection of seawater into any part of the nuclear reactor or the Nuclear Steam Supply System itself. It is an injection of seawater into the containment structure surrounding the reactor pressure vessel.
These reports confirm my earlier prediction that they were not talking about actually putting seawater into the nuclear steam supply system, despite the lack of any previous clear, sensible announcements in the press to this effect.
Given that the reactor pressure vessel is completely intact and the control rods were fully inserted, normally, by the Reactor Protection System at the first sign of the earthquake, and the reactor is in a completely subcritical configuration, adding additional nuclear poisons (i.e. boron) to the system is seriously overkill; there is no pressing reason why it’s really necessary, other than to be extra conservative.
ASIDE: “Going critical” isn’t some kind of catastrophe, it’s what a fission reactor is designed to do, which it normally does under normal operating conditions.
Status of Unit 2
Over March 14 and March 15, Unit 2 has been in a similar low-coolant condition to Unit 1, with coolant water being boiled off through the torus, and with the Emergency Core Cooling Systems, such as the Low Pressure Coolant Injection system, operating.
Some kind of explosion was detected in the Unit 2 reactor building on the 15th of March, in a different area to the hydrogen ignition in Unit 1 and Unit 3. This hydrogen explosion was possibly within or close to the torus (the toroidal overpressure-supression tank), which is below grade, near the bottom of the reactor building.
Although this explosion may have damaged the torus, it has not damaged any of the real containment structures, such as the primary containment structure, the drywell, the reactor pressure vessel, or the outer reactor building.
There are valves that can be closed to isolate the vents that connect the torus to the drywell. Therefore, even if the torus was damaged or breached, it can be isolated from the drywell, meaning that there’s no real pathway between the drywell (the primary containment vessel) and the reactor building, through the damaged torus.
That means that your key layers of containment are all still intact.
Status of Unit 3, and its MOX fuel
There has also apparently been a loss of some of the normal reactor coolant systems in Unit 3, and the precautionary injection of borated water into the primary containment vessel, as at Unit 1, also began on March 13 and continued through to March 14.
As with Unit 1, seawater has been being injected, in addition to fresh water, but it is into the drywell – not into the reactor vessel. There has also been a hydrogen explosion in the rooftop refueling crane space above the reactor building at Unit 3 – very similar to the explosion in the same area at Unit 1.
Fukushima I Unit 3 is currently fueled with MOX fuel, containing recycled plutonium dioxide in its initial fuel load, in addition to low-enriched uranium dioxide.
You might see some slightly different characteristics in this MOX fuel with regards to things like the void reactivity coefficient compared to ordinary LEU fuel, because the fission cross section, plotted as a function of the incident neutron energy, will look slightly different for 239Pu compared to 235U. So, if the cross-section doesn’t drop away as rapidly as you increase the incident neutron energy, for 239Pu as compared to 235U, then you might see a negative void reactivity coefficient that isn’t quite as strong. Stuff like that.
But in practice there’s no evidence that we’re seeing any neutronic behavior or thermal behavior in the fuel that is any different, in practice, as far as the emergency situation is concerned, at Unit 3 as compared to Unit 1.
There is no significant difference in the composition of the radioactive fission products, or in their potential to be released to the environment, in the MOX fuel compared to the LEU fuel in the other reactors.
What we will see, however, is a lot of “plutonium phobia” in the media with regards to this MOX fuel, which is completely independent of any rational, fact-based discussion of the science and engineering. There’s this idea in the popular consciousness that plutonium is some mysterious, almost mythical, horrifying and terrible thing, and you’re going to turn inside out and die if you ever even look at it the wrong way.
But plutonium isn’t something that’s been spawned out of the arse of a demon or something, it’s actually just another element. It’s radioactive, but less radioactive than most of the fission products formed in a nuclear reactor.
The potentially harmful radioactive materials that might be released into the environment from a LOCA scenario such as the Fukushima I-1 situation, or the Three Mile Island accident, are the radionuclides of the high-volatility fission products, such as radioisotopes of xenon, krypton, and to a lesser extent, radioisotopes of iodine. Tritium is also on the list of key radionuclides that are present within the coolant water and are volatile enougn to potentially be relased, but its relatively low specific activity compared to the hort-lived fission products and its very low beta decay energy means that tritium is not significant in terms of its potential for harm.
Uranium and plutonium, for example, are heavy metals, they’re not soluble in the coolant water, and they are nowhere near as volatile as these gaseous and volatile fission products. This means that there’s no way that these elements can escape out into the primary coolant and eventually find their way out into the reactor building atmosphere, as these more volatile elements can. This means that there’s no way that they will be released out into the atmosphere in the same way that very small quantities of tritium and gaseous fission products may be be released. Even if they could be, uranium has a negligible specific activity, and it is a negligible source of radiation dose – and plutonium is not extremely radioactive either; being less radioactive than the majority of the fission products.
The Used Nuclear Fuel
There is a small fuel transfer pool in the reactor building at each of these GE BWRs, near the top of the reactor pressure vessel, that is used for the temporary transfer of used nuclear fuel during refueling. However, the longer-term storage of the used nuclear fuel is done in a pool elsewhere on the site. Those storage pools, outside the reactor buildings, are seismically hardened and defended-in-depth, just like the reactors themselves, and there are no indications of any problems with them. Since there was no refueling going on at the damaged reactors at the time of the earthquake, there is little or no fuel in the fuel transfer pools.
That’s my understanding of the situation, anyway.
Is there actually some used nuclear fuel stored in the Unit 4 fuel transfer pool at the time of the earthquake? I don’t believe there is much, if any.
Some media reports suggest there might be; but I’m extremely distrusting of the incomplete, garbled information being filtered out through the mainstream media on this whole issue – which is why I’m trying to patiently take information in from a diverse range of sources, and to patiently, carefully and skeptically piece it together into a self-consistent picture of what we actually know about the situation, based on my knowledge of the physics and my limited but partial knowledge of nuclear engineering.
If there is some fuel stored in the transfer pool, we need to know a few things about it.
How much is stored there? How long has it been there for? When was the reactor that it was taken from powered down, prior to fuel unloading? The decay heat of used nuclear fuel drops off exponentially following reactor shutdown, as the short-lived fission products that account for most of the radioactivity rapidly and exponentially decay. After a short period of cooling, the used fuel would not be significantly heating the pool water, nor would it require active cooling.
Immediately after fission is shut down in an operating nuclear power reactor, the power output from nuclear fission ceases. However, the nuclear fuel is still extremely radioactive, at least initially, due to the presence of very short lived fission products with very high specific activities. But that decay heat output falls off exponentially over the coming hours, as the very short lived fission products decay.
Thanks to Kirk over at Energy From Thorium for preparing this excellent chart, which I’ve borrowed from the EFT blog – all credit to him. Go and check out Energy From Thorium – it’s an excellent site.
Initially, the decay heat power level – the heat emitted by the radioactive decay of the radionuclides present in the used nuclear fuel, in a subcritical configuration – is approximately 5% of the fission reactor’s normal thermal power output.
The Fukushima I Unit 1 reactor has a nameplate capacity of 460 MWe. At a thermodynamic efficiency of approximately 35%, the reactor has a thermal power output of approximately 1.31 gigawatts.
Therefore, immediately following reactor shutdown, the decay heat power output from the reactor’s nuclear fuel will be about 5% of that, or about 66 megawatts.
Over the last 5 days since the shutdown of the reactor, however, that power output has been dropping off exponentially, and it is now somewhere down around 6 megawatts of thermal power.
So, how much fuel is presently stored in the Unit 4 fuel transfer pool, if any? I might take an educated guess and say that it’s about one third of one full core loading, since about one third of the core fuel is replaced during one refueling. Let’s take a conservative guess, and say that it has been out of the Unit 4 reactor (which was already offline for maintenance prior to the earthquake) for about a week, at the least. It’s probably longer than that.
If those assumptions are valid, then the radiothermal power output from the used fuel in the fuel transfer pool will be only about one or two megawatts at the present time, and still decaying of course.
We know what the thermal power input from the fuel is, what the volume of water in the pool is, what the dimensions of the pool are, what the nominal temperature of the pool is, and what the specific heat capacity of water and the latent heat of evaporation of water are.
Therefore, we know exactly what the temperature of the water of the pool is going to do, and exactly what the volume of water in the pool is going to do. There is no need for guessing or speculation.
The nuclear fuel is made up of pellets of uranium oxide clad in tubes of Zircaloy. (Zircaloy is the trade name of the alloy in question, which is almost pure zirconium.) UO2 is a refractory metal oxide with a very high melting point – it is not flammable or combustible in any way at all. It does not burn. In theory, the zirconium metal cladding could burn, if it was removed from all cooling water, exposed to an oxygen-containing atmosphere, and heated to an extremely high temperature. However, it is almost impossible to burn a piece of zirconium in this fashion in practice.
The rate at which the water in the fuel transfer pool would evaporate, in the absence of active cooling system functionality and in the presence of the fuel’s remaining thermal power output, is not more than a few percent of the water volume per day.
Given that there is approximately 16 feet or more of water above the surface of the fuel assemblies in the pool under normal conditions, it will take many days to weeks for this water to evaporate to the point where the fuel is potentially exposed above the surface, assuming that no additional water was added by any other mechanism.
The outermost layer of the multiple layers of containment surrounding the reactors – the cuboid-shaped reactor buildings – have walls and a roof made of solid concrete. On top of the concrete reactor buildings, however, there is an additional part of the structure – it is not made of concrete, but it is made of steel, with steel sheets over a steel frame. This steel building on top of the reactor building houses the fuel transfer crane, and it is built on top of the concrete roof of the reactor building.
That is, the part of the structure above the concrete shield plug and the refueling platform at the top of the concrete reactor building, as shown on the diagrams below.
It is this relatively weak steel structure on top of the reactor building, which is not really part of the reactor building proper, which has been blown out by a hydrogen explosion at Fukushima I Unit 1, as I described in my previous post, and apparently at one of the other Fukushima I reactor buildings as well.
The concrete roof of the reactor building proper – which is not where the hydrogen explosion occurred – is built over the top of the temporary fuel transfer pool; the pool is protected within the concrete reactor building.
Unit 4 Explosion and Fire
On 14 March, an explosion of hydrogen gas in the steel-framed structure atop the Unit 4 reactor building occurred, similar to the earlier explosion at Unit 1. As was the case at Unit 1, there was no real damage to the reactor building proper or any of the other layers of containment within.
On March 14, a fire was reported in the Unit 4 reactor building. The fire was caused by a leak of lubricating oil in the mechanical drivetrain that drives the reactor’s recirculation water pumps. Contrary to inaccurate information which was spread widely in the media and the social-media grapevine, this small fire had absolutely nothing to do with the used-fuel transfer pool or any fuel which may have been in it. The fire was extinguished shortly after.
Detection of radioactivity off the coast
It has been reported that the crew of the Nimitz-class carrier USS Ronald Reagan, off the Japanese coast, has detected the presence of radioactivity emitted from the Fukushima nuclear power plant. Since she’s nuclear powered, the vessel is obviously carrying sensitive instruments and sensors for detecting the presence of radioactivity around the ship, and obviously they’ve detected the trace levels of radioactivity that have escaped into the atmosphere.
It’s possible to measure the presence of small traces of radioactivity fairly easily with extremely high sensitivity. Just because we’re able to accurately measure it and quantify it at very low levels doesn’t mean we’re dealing with levels of radioactivity that are anywhere close to harmful levels.
Has anyone actually reported the actual quantitative presence of radioactivity that was detected aboard the ship?
The status of the Fukushima II plant
At the time of the March 11 earthquake, all four operating units at the Fukushima II station were automatically SCRAMmed by the Reactor Protection Systems.
Although there were some reports of disruptions to the Emergency Core Cooling Systems at Fukushima II, all the Emergency Core Cooling Systems at all the reactors were restored to operational status.
Between March 12 and March 14, every one of these reactors has been bought to a safe state of cold shutdown, where the decay heat from the nuclear fuel is being completely dissipated and the fuel is being kept cool, with no rise in fuel temperature.
Brave New Climate 
195 replies on “Fukushima redux – design basis Godzilla?”
Nikkei:
Do you have any nuclear training or operational experience or are you simply an interested observer?
Think hard about the geometry of a helicopter that is 1000 feet over the Fukushima Daiichi power station and then goes down to 300 feet.
Do you really believe there is any way that a measurement reported as being over unit 3 will be much different from one that is reported as being over unit 4?
Have you seen photos of the station to see just how close those two buildings are?
The report that you are quoting probably came from a source that mistook milli for micro. What the heck, for a journalist they look pretty similar – but they are a factor of 1000 different from each other.
What would you rather have for your annual salary 10,000 or 10,000,000?
Yes, I make no bones whatsoever that I have an agenda. I want to help make the world a better place for my children, grandchildren and their grandchildren by helping us to move from a hydrocarbon based economy to a heavy metal (uranium, plutonium and thorium) based economy.
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Thanks for all the comments.
Responses to previous comments in a roughly chronological order:
“What may be the source of the high levels of radioactivity?”
Hard to say, specifically. I would say it’s the release of fission-product gases (Xe and Kr) from the fuel assemblies as they are heated to abnormally high temperatures.
I would say it’s mainly from the reactor(s), not used fuel in the storage pool.
“The reactor was taken offline on Nov 30, per IAEA by the way.”
There’s a useful little piece of information. Thanks for that. That does seem like a rather long maintenance and/or fueling outage, doesn’t it?
“It might be extremely cynical, but there is a magnitude of earthquake that will cause all buildings to collapse, killing all inhabitants and obviously it doesn’t matter then that the reactor doesn’t survive – as long as the effects remain local. Perhaps successful SCRAM wold suffice for that.”
To re-express that in a perhaps less cynical way – I absolutely agree that we need to keep this all in context with regards to the terrible tragedy and destruction across Japan.
“I have one question. Is your fission power display graph dependent on some level of cooling?”
No. This is the intrinsic amount of energy that is being emitted by the radioactivity in the nuclear fuel. These figures have nothing to do with what kind of cooling is or isn’t working.
However, to figure out the temperature that the fuel will rise to, you’ve got to look at how much power generation there is from the radioactive fuel, and how that power is being dissipated, which means looking at the cooling mechanisms that exist.
“The other thing Barry Brook probably regrets claiming, is that these containment vessels will contain the fuel no matter what. That is simply nonsense. I think it comes from the misunderstanding about any original claim or design specification–which assumes some level of cooling. Once you have inadequate cooling, forget it. With full meltdown the fuel forms a pool which heats even more than the pellets–because it is no longer moderated. It can never approach criticality–ie. like a nuclear bomb, but low level fission continues so it just keeps heating up. At a couple thousand degrees (if not before, remember there will be intense steam pressure by then, it is like a massive pressurized can) the steel will melt or soften enough for welds to give etc. By memory (dangerous but you can Wiki this) it can reach up to 5000 degrees so absolutely nothing can contain it.”
That’s an extent of core melting that is the worst case imaginable, complete liquefaction and melting of all the fuel, and I don’t think it’s realistic. That’s a scenario far, far worse than Three Mile Island, for example.
Remember that the energy being generated by the radioactive fuel is constantly dropping and dropping every day as it decays.
Even if you imagine that the used nuclear fuel could get through the reactor pressure vessel, which isn’t realistic, there are still multiple other layers of containment – including the massive concrete primary containment structure that is immediately surround the drywell – that it has to get through before it can potentially hurt people.
“My questions are regarding the apparent gaping hole in the side of the #4 containment building?”
I’d like to see a good photograph of that. Does anyone know where to find one?
“Except the fact that the pool on 3 and 4 have COMPLETLY evaporated”
Got any source material or anything to back that up?
“and are emitting enough radiation to kill or incapacitate anyone near the pool.”
Yes. Everybody here knows that. Standing near used nuclear fuel which is not contained in any water or any other kind of shielding is extremely bad for your health.
The people working at Fukushima know that. This is not any kind of novel information. And it’s not particularly significant.
If the used nuclear fuel is exposed without water present, the people at Fukushima won’t be standing near the fuel transfer pool.
“Unit 4 was in a refueling outage and had offloaded the complete core for a vessel inspection. They have a complete core plus fuel still cooling off from the previous outage. It has the most fuel in the pool compared to any others. That is why the NRC has made statements that they have about the most of the water being boiled off. They now the number of sticks in the pond and the decay heat curves plus the info of the SFP temp last reported (84C I believe). Its not to hard to calculate the results.”
Thanks, that’s good information. OK, we know that there certainly is fuel in the pool. And we know exactly how much there is, how old it is, and how hot it is.
I wonder how long they hold they fuel in the reactor’s on-site pool for prior to transferring it to either the main fuel pool on the site (outside the reactor buildings) or into dry casks.
“Luke could you provide some more context for the comments below from your blog..”
Obviously that post was written several days ago. We all know that this situation has been developing and changing quickly, with information becoming “outdated” rapidly.
“Luke,
You state that only a small proportion of used fuel from a given reactor is stored in the pool adjacent to it. This is at variance with most (all?) mainstream media reports, which claim that essentially all of the used fuel rods are there.”
OK, the information at the present time does show us that there is at least one full core load of fuel in the pool at this time.
It’s OK to say, in a polite sensible way, “Luke, actually that appears to be wrong and here are the details”. I appreciate that. I welcome it.
Peer-review and sensible, constructive corrections and updates to the information that we post (Barry, myself or any other commenter or poster) are all very valuable and important. Constructive, sensible comments that review or correct or provide updates to the information somebody else has posted are all important.
We’re all working with limited and imperfect information here, trying to collate and filter all this information into a picture of the situation which is consistent and accurate and sensible, in a situation which is developing and changing rapidly.
Many hands make light work, as far as achieving this is concerned.
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New JAIF status grid (until 3/17 16:00)
Click to access ENGNEWS01_1300350525P.pdf
The “Remarks” section says explicitly:
“Immediate threat is damage of the fuels in the fuel pool outside the containment vessel at uni-3 and unit-4. To improve the situation of lack of water in the spent fuel
pools at uni-3 and unit-4, the self defense force started operation for filling the pool with water in 09:48 of March 17. This operation is to drop a huge bucket of seawater
from a helicopter. In addition, watering from the ground by high pressure pump is to be prepared.”
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I spoke with an old friend yesterday. I cannot reveal his name, but rest assured, he is in a position where his information is extremely reliable.
He told me that the response center at the US NRC has no source of information on the ground that is any different from what we all have access to on the web. There is no reason to believe they are especially well informed. If you watch Dr. Jaczko’s testimony on C-Span, you will hear him using “We believe” and awful lot, and you will not hear him claiming any specific source of information.
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“And why are the pools heating up, when you claim they shouldn’t do so?”
In this house, we obey the laws of thermodynamics!
I never said the pools shouldn’t heat up. Of course the fuel is releasing energy. But releasing energy at what rate, into how much water?
“And since we know that the fuel rods have been partially (and in the case of unit #2 possibly fully) exposed, are you saying they are maintaining two separate water pumping systems, fresh water for the reactor vessel, seawater for the drywell?”
I don’t understand this seawater business completely. Perhaps you can explain it to me?
We know that seawater injection is occurring into the reactor containment vessels at certain reactors – but that’s not to say that it may not be into the reactor pressure vessel too.
But given the damage it will do to the nuclear steam supply system, that seems to me like it would be an absolute last resort – and I do not yet actually have a good understanding of why you would resort to that.
Most of the components of the ECCS – the HPCI, the RCIC, the LPCI – are designed to work in station-blackout conditions.
Have RCIC and LPCI actually failed at all these reactors? If so, I’m curious to actually find out how.
LPCI is designed to, in the event of a severe design-basis LOCA, supply plenty of water to the core continuously over several days while the fuel’s decay heat drops away, until cold shutdown is reached.
Even if, through some mechanism that nobody has yet elucidated to me, LPCI is not functional, there is a very large amount of fresh water stored in the system which is used to actually supply the LPCI water. Even if the actual LPCI pumps aren’t running, why can’t that water be pumped in instead of seawater?
“Good job on getting concise no-nonsense information out. But I think Luke needs to re-think some of the information about these pools. For example unit 4 has more fuel in it than you are assuming.”
Thanks; see my comment above :)
“Glad that PRA is finally being discussed! Watching the hearing on the Hill today was frustrating. Sen. Boxer was harping on the fact that the plant in Japan was “only” designed for a magnitude 7.5 (or whatever the correct magnitude is, I’m not sure), but not for a magnitude 9.0.”
The design basis really doesn’t have anything to do with the earthquake magnitude, because it depends on how far away the earthquake is, and how deep it is, as well as it’s magnitude.
The earthquake design basis is based on the peak ground acceleration that could occur, as measured at the plant site, under earthquake conditions.
What was the actual peak ground acceleration measured at Fukushima? What was the design basis? These are good questions, I would like to know.
“If seawater is not being pumped into the core, what isthe use of adding boric acid to it. Outside the pressure vessel, this boron will have little if any neutron absorption effect.”
Good question. Why is the boron needed at all?
There is no fission going on at all. No fission can occur in the reactors. They had all the control rods fully inserted normally, during the initial SCRAM at the time of the earthquake.
Even if you melted the entire core into a pool of molten corium on the bottom of the reactor pressure vessel, that pool of molten uranium oxide and zircaloy and molten control rods wouldn’t be critical, especially without the neutron-moderating water that is required for the LEU to reach criticality.
The used fuel in the pool can’t reach criticality, either. The used-fuel storage water is normally borated, and it’s in a subcritical geometry. If the water in the pool evaporates, the boron is only concentrated. If all the water was lost, you’re removing the moderator, so there will be no criticality in that scenario either.
Maybe it’s just standard operating procedure in these plants that all emergency coolant injection has boron added to it, as a routine procedure, just to be extra safe and conservative?
“What I can say is if the EDGs had been placed on top of the bluff and just cables run down to the reactors, then this accident would have been a non-event. This would also have separated the EDG fuel from the reactors.”
This certainly makes sense. I’m sure it is one of the key considerations that will come out of this incident for all future nuclear power plant build.
“What this accident reminds me of is the events that lead to the SUBSAFE program. We didn’t stop building subs, but we took a long hard look at design and construction.”
Good analogy. I have no doubt that people will be taking a long hard look at design and construction in the nuclear energy industry now. And just like with SUBSAFE, something that is already quite safe will be made much safer. I just hope that irrational political pressure doesn’t put an end to the whole submarine force, to use your analogy.
“The generators could keep producing power for as long as the heat lasts and of course, once the heat is no longer significant, the power is no longer needed.”
As I understand it, HPCI is driven by steam from the nuclear steam supply system, but it can only be operated for a limited amount of time following shutdown, because the decay heat power output isn’t enough to raise enough steam.
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2nd 3/17 release is up at
http://www.nisa.meti.go.jp/english/index.html
covers up to 7:30 so a good 12 hours behind the times. (what time zone are these times in ? Japan? GMT? (i’m assuming local time in Japan))
This was the first i saw this document at all. Good timeline there. Looks like among the workers there have only been two severe casualties, which is 2 workers still listed as “missing” in the unit 4 bldg for almost 2 days now. (i hope they’re ok, but seems like a longshot).
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@Steve Gardner, et. al. Your basing your reasoning on the supposition that there would be greater long-term impacts from a worse-case event at a nuclear plant, than at any other facility. This is categorically and demonstrably wrong. As I alluded to in my last remark, even Chernobyl did not seriously effect the surrounding countryside, even though a graphite fire is the most ideal way of generating, and broadcasting radioactive contamination, short of an atomic bomb.
The fact is that both the short-term, and long-term consequences of loss-of-containment event at a nuclear reactor have been blown far out of proportion by governments and the media. While the former had some excuse, in that there was little hard data available, forcing them to consider worse-case predictions based on poor models, it is high time these were reevaluated in the light of real-world observations.
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“People have to be in panic to do things as foolish as take iodine pills when they are thousands of miles away. They don’t know basic things like that there has always been natural background radiation. They don’t know how big a millisievert is. They don’t know how big a lethal dose is. And they don’t know that TV journalists don’t know anything about it.”
Very, unfortunately, true.
“…the operators were injecting sea water into the Reactor Pressure Vessel (RPV) of Unit 2 and into the Primary Containment Vessel (PCV) of units 1 & 3. Can you interpret their teminology for me?”
The RPV is the reactor vessel itself. This bit is new news to me. The PCV is the containment vessel – and this information is consistent with what I originally posted.
“Luke – It makes no sense to me to inject seawater (SW) into the annular volume between the Rx vessel and the primary containment.”
It has been reported that they’re actually doing it, and possibly also injecting into the reactor pressure vessel at one of the reactors too. If you don’t have a good understanding of why that’s necessary or why that makes sense, well, you and me both.
“I think your flowpath only makes sense if the operators do not have working high-pressure pumps and/or electricity to power them, so they can’t get water into the Rx vessel against the pressure.”
I thought this kind of thing was all supposed to be handled by normal ECCS operation, anyway. Initially, HPCI is used while the core is still under pressure, and then if HPCI can’t do the job and LPCI is required, the RPV is depressurized, if it is still at pressure, and the pressure is maintained sufficiently low that LPCI can keep running water into the core.
“A reader at the MITNSE blog provided this link to a TEPCO slide presentation of 16 November 2010 PDF). Slide 9 shows the status of the spent fuel pools and the separate on-site longer-term storage facility.
As of March 2010, there were 3,450 fuel assemblies in the four pools at the reactors, an average of ~900 per pool. A reactor core contains about 600 assemblies (I’m not sure about that number).”
Thanks. We now have a good, clear understanding of how much used fuel there is here, and the fact that most of it has had several months of decay already.
“There has been report of LOSS OF LIFE of at least one worker:”
Of all the people, perhaps on the order of ten thousand people, who have tragically lost their lives in this earthquake and tsunami, who have lost their lives in a disaster completely unrelated to any exposure to radioactivity or ionizing radiation, one of those people was on-site at the nuclear power plant.
“Can it heat up to the equivalent of a partial meltdown? I’m no expert and do not know. But at minimum I’d expect those rods, especially if exposed, to be very happy to oblige the no-nukes and provide abundant cesium and iodine injections straight into the environment.”
It won’t melt. How hot will it get, in air? It depends on how long the fuel has been cooling for, and what its decay power is. Should be quite straightforward to actually plug the information into the right software and get concrete numbers, assuming actual uncovery of the fuel in the pool.
In the absence of water cooling, I think it’s plausible that it could get hot enough for a release of some of the fission-product gases, i.e. radioisotopes of Xe and Kr, though. But most of those short-lived fission products have decayed already, so the inventory will be quite limited, except for the ones with half-lives that are a bit longer but have less specific activity, eg. krypton-85 in particular.
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“The answer to the question, “why would a worker just sit around in a high dose area” seems to be, “Because that’s where they have to be to get their job done.”
I’m really not concerned much with what the dose rates are in the plant itself.
The men and women who work there understand dose rates and health physics quite well. They routinely work in areas of elevated above-background dose, and they know how to work safely in those environments. They understand how to measure and quantify the radiation field in the working environment, and the accumulated doses that they’re personally receiving.
They understand how to manage shielding, exposure time, radiation measurement and dosimetry in order to get the work done safely and effectively.
Even with abnormally significantly elevated radiation fields in some areas as a result of these incidents, they still know how to work safely. If the radiation dose rate in some particular area is so highly elevated that it cannot be entered safely for any length of time at all, then they won’t be entering it.
I’m much more interested in off-site dose rate measurements, personally, as those are the measurements that are actually of relevance to the public.
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“Hydrogen is produced, when the outer shell of the fuel rod (zirconium) reacts with steam/water. It can be produced either in the SF pool or the reactor. There has been massive amounts of hydrogen produced and one of the main issues past couple of days, has been the proper venting the Hydrogen.”
For this to occur, the fuel assembly needs to be in water. If there is no water this cannot possibly occur.
Furthermore, the fuel assembly needs to be at an extremely high temperature for this to occur.
This can occur, in the event of active cooling loss, in fuel that has been removed from an operating critical reactor only very recently, since the fuel’s decay heat decays away quite rapidly.
The used-fuel heat output is just not that high in this fuel, which was taken offline 3.5 months ago. This kind of reaction will not occur, based on the fuel-pool temperatures that are being reported.
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@Luke
“Most of the components of the ECCS – the HPCI, the RCIC, the LPCI – are designed to work in station-blackout conditions.
Have RCIC and LPCI actually failed at all these reactors? If so, I’m curious to actually find out how.”
They primary ones have failed some time ago. Check the jaif reports. For example http://www.jaif.or.jp/english/news/2011/110314fukushima_event-status-1.pdf
Newer editions switched to a different terminology as in http://www.jaif.or.jp/english/news_images/pdf/ENGNEWS01_1300350525P.pdf
Barry actually has a post in this very blog that shows the most recent report (and he keeps it updated).
“there is a very large amount of fresh water stored in the system which is used to actually supply the LPCI water”
It is my understanding that this is exactly what is not true: they are using seawater because they do not have fresh water and they cannot be resupplied.
@DV82XL
I agree. I’m no expert but I believe that even if there’s a total core meltdown followed by an explosion that destroys the containment vessel, stuff would be thrown a few hundred meters up but there would be no long term fire to bring it further up as in Chernobyl.
Also I believe the real danger for people is not going to come from direct exposition. It’s going to come from water and food. And this is something that can be controlled.
Of course “can be controlled” does not imply “will be controlled”. That’s why I wrote that this is no Chernobyl (even in the worst case) unless we make it so.
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Many thanks Luke for taking the time to go through all these comments. I certainly appreciate your efforts and all those of the other contributors also.
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so its confirmed that there are people on this blog that think the Japanese governments request for people to evacuate is emotional/hysterical. I’d suggest that you are living in a degree of denial of the situation.
And to the extent that Luke Weston has acknowledged that his earlier sunny statements on the severity of the incident were completely wrong, that’s appreciated. Perhaps the nuclear booster side of the argument could do what they are suggesting to others and reduce the slightly hysterical edge to their apparent desire to insist that all is OK continually and as has been said wait for the facts before pronouncing this as some kind of victory for nuclear energy. Its starting to sound a tad strained.
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@Jim – I am not living in a state of denial. I have been studying and practicing my nuclear knowledge for 30 years. I know far more about the subject that most people alive.
I know that sounds incredibly arrogant. Sorry.
The fact is that panicking about minor amounts of radiation in the face of a huge natural disaster is putting a lot of lives at risk. The nation of Japan needs food, water, and shelter. It does not need to waste resources on actions at an industrial facility that are challenging for the workers, but not putting anyone at risk. I am staking my reputation and my career on being correct with my analysis.
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@Rod. Sorry Jim but what you are saying is that you know better than all the authourities tasked with actually ( as opposed to theoretically and virtually) dealing with this incident. Those authourities, unlike you, have to deal with potential real risks rather than textbook optimistic possibilities. I am just suggesting that people should enterain the idea that they might be wrong, I’m happy to do that on my side, you seem to be locked in a kind of dogmatic trench warfare due to your faith in the technology. I think neither us can afford dogmatic positions in this. The reality on the ground is that this nuclear accident is making a shocking tragedy far worse for many people. We are all hoping its fixed soon, but the repeated over optimistic opinions and statements of the incident’s triviality on this site are not grounded in reality.
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fp: With the water moderator gone, the reaction (if any) will slow down if anything. I must be missing something here.. Why is this a concern at all??
Yes. You know nothing about nuclear reactions or power. Your own sentence explains it – “moderator” means to slow down. “accelerator” is the word you need for your argument to make sense.
Without the water moderation (let alone cooling) the reaction will speed up, and things will get hotter.
On a different note: on the 15th it was at 84 C. That’s not a very scary rise in temperature, considering the fuel rods melt at 2000 C.
84C is not far below where water boils (100C) and after it’s gone there’s not moderation and the heat will go up until it reaches an equilibrium with distribution to the surrounding environment. If that distribution is only air – well air is not a great conductor (without significant significant circulation) else your car would be a Volkswagen and not water cooled. This is a basic principle of thermodynamics.
There are too many people on this site who have no – read zilch – understanding of basic physics.
And I include Luke in that category as a result of this comment:
if the cross-section doesn’t drop away as rapidly as you increase the incident neutron energy, for 239Pu as compared to 235U, then you might see a negative void reactivity coefficient that isn’t quite as strong. Stuff like that.
That is not a very usual use of the term cross-section and it turns the phrase into meaningless gibberish.
A cross-section is a probability, not a magnitude. It doesn’t matter what the input intensity is, the cross section remains the same.
Or if perhaps another, non-standard usage is intended perhaps Luke could explain.
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A Tepco official has told a press conference in Japan that radiation levels at the site soon after 9.30 am were at 3,750 millisieverts per hour
What are the implications of this level of radiation?
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@Jim – do you have a link? Are you sure it was milli and not micro?
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@ Rod- that was sourced from the Guardian newspaper so no I’m not sure, you’d have to check their source.
Meanwhile just acknowledging that Barry has posted the below statement on another part of his blog and would appear to disagree with some posters now on the potential seriousness of this event. The acknowledgement that his prediction of the seriousness of the event being severly underestimated by him is welcome.
” My initial estimates of the extent of the problem, on March 12, did not anticipate the cascading problems that arose from the extended loss of externally sourced AC power to the site, and my prediction that ‘there is no credible risk of a serious accident‘ has been proven quite wrong as a result. It remains to be seen whether my forecast on the possibility of containment breaches and the very low level of danger to the public as a result of this tragic chain of circumstances will be proven correct. For the sake of the people there, I sure hope it does stand the test of time.”
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It seems that fp and JM are both confused. The moderator in a reactor is for slowing down the neutrons to make them more likely to be absorbed. There is no “moderator” in the cooling ponds because there is no sustained chain reaction going on. The point of the surounding water is simply to cool and shield.
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“That is not a very usual use of the term cross-section and it turns the phrase into meaningless gibberish.
A cross-section is a probability, not a magnitude. It doesn’t matter what the input intensity is, the cross section remains the same.”
“Intensity”, as in, say, the intensity of a beam of neutrons, is not the same thing as the energy of those neutrons. Intensity, in this sense, is like a measurement of the particle flux – and you’re quite right, a cross-section for a particular nuclear reaction does not depend on the flux or intensity of the incident particles.
But the cross-section for a particular nuclear reaction – for example, fission induced by a neutron, in some fissile nuclide – does change as the energy of the neutrons changes. Like this, for example: http://t2.lanl.gov/tour/u235nf.gif
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Luke,
You have gone through the thread, and responded in three or four recent comments of your own. There is some information at variance with what you wrote in the original post, that you have acknowledged.
It would be helpful for this site if you would write a (timestamped!) Update to the original post, clarifying the major points where your original analysis was incorrect.
Most readers will not work through a long thread to discover your remarks, as they stand. They will be left with misunderstandings.
Thanks.
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@JM
“fp: With the water moderator gone, the reaction (if any) will slow down if anything. I must be missing something here.. Why is this a concern at all??
Yes. You know nothing about nuclear reactions or power. Your own sentence explains it – “moderator” means to slow down. “accelerator” is the word you need for your argument to make sense.”
Actually he sounds more knowledgeable than you. In a reactor the role of a moderator is to slow down the neutrons. Fast neutrons are unlikely to cause fission, slowed down neutrons (aka thermal neutrons) are much more likely to do so. Remove the moderator and you have a less energetic reaction (or none at all).
“84C is not far below where water boils (100C) and after it’s gone there’s not moderation and the heat will go up until it reaches an equilibrium with distribution to the surrounding environment. If that distribution is only air – well air is not a great conductor (without significant significant circulation) else your car would be a Volkswagen and not water cooled. This is a basic principle of thermodynamics.
There are too many people on this site who have no – read zilch – understanding of basic physics.”
Eventually there is someone with an understanding of basic physics that believes nuclear physics is as simple as thermodynamics.
Remove the water and you remove the moderator. If there was a chain reaction, this would slow down, not go up. But there’s no chain reaction: only decay (of both actinides and fission products, but fission products are the ones that generate the most energy for the first 45-50 years after the chain reaction has been stopped). Therefore the absence of the moderator does not influence heat generation.
However without water there is less cooling implying higher temperatures. The zircaloy will oxidate. The higher the temperature the faster it oxidates. It can oxidate in steam or just in the air (as long as there is oxygen, of course). If it happens in steam hydrogen will be a by-product (in large quantities).
Zircaloy oxidation (both in steam and in air) also generates A LOT of heat in and by itself. While the zircaloy will only melt at 1850°C, the oxidation process can become self-sustaining at much lower temperatures (I’m not sure, I think around 1000°C).
I do not know if it is possible to reach such temperatures in those pools and risk a “zirconium fire”. Even if it cannot happen as soon as the rods are not covered by water, the strongly exothermic nature of zircaloy oxidation itself will start adding heat.
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It seems to me to be very unlikely that the water levels in the spent fuel pools (SFPs) could have been greatly lowered by evaporation and boil-off, since the pumps stopped circulating the water on 3/11/11. Luke’s heat-generation calculations seem to indicate that. (Luke, has your view changed?)
During the earthquake, I think that the facility suffered over-design levels of ground acceleration (is that certain?). Since then, there have been explosions and fires near some of the four SFPs.
Figure 20 in the original post shows that the Mark I design has the SFP located near the top of the secondary containment. It is not at ground level.
Taken together, a simple explanation is that some of the SFPs may be leaking. The leak would come from broken pipes, or from cracks in the reinforced concrete.
Has the presence of leaks been confirmed or denied? If confirmed, are there any estimates as to their scope, in liters/hour?
A big leak would seem to require a major change in strategy, as that would make it impossible to re-fill an SFP.
Which is worse, assuming some fuel rod cladding is already damaged and that the rods have lost their integrity: having fuel rods in the SPF go dry and overheat? Or spraying water on them, which turns to billowing steam on contact, possibly entraining heavy radionuclides like I, Cs, and Sr, and carrying them into the atmosphere?
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@AnalogFile – Even in the very worse case that could possibly occur here, the food chain will not be effected, and nether will water supplies be impacted in any meaningful way. The mobility of the radioactive products, and their lack of solubility will keep them from spreading.
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I would simply request that all statements in any ‘expert’ update/information step in this episode properly accept and give weight to the fact that much is unknown about where we are, how we got here, and what can happen next to each component given that the plant and its parts are now operating so far outside off normal or modelled status, so far away from operator experience, and that the cruel world out there has a habit (a particularly vicious habit in this case) of shifting the sand on ya.. A healthier respect for the as yet ‘unforseen’ please…in an otherwise really useful update. Thanks.
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That’s where I stopped reading.
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“What if the next earthquake is magnitude 10? Magnitude 12? Magnitude 20? But where does it stop? Where do you set the design basis? What if the reactor is attacked by Godzilla?h.”
Considering the number of major earthquakes with tsunamis japan has had in living memory the only appropriate reply to a statement like this is vulgarity.
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I won’t respond individually but this sort of statement is nonsense:
Remove the water and you remove the moderator. If there was a chain reaction, this would slow down, not go up
So am I to understand that you stop the reaction in a reactor by removing the cooling rods????
That in an earthquake you should lift the rods out of the reactor rather than drop them in?
You guys are in fantasy land.
And as regards heat it is relevant. Go and get a saucepan, fill it with water, attach a thermocouple and put it on your stove. Plot the temperature.
The temperature will rise to 100C where the water starts to boil. It will then stay there and not move until all the water is gone.
At that point the temperature will start to go up again until the pan melts and starts to burn. That’s what they risk happening with the fuel rods in those ponds.
For another perspective consider this:
– why are these rods put in water in the first place?
– why does it become so dangerous to go near them if there is no water?
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JM, I don’t understand the point you are making. There is no such thing as cooling rods. There are control rods, which are strong neutron absorbers (usually boron/cadmium). And I think the folks were talking about the possibility of recriticality in the SNF ponds, not the reactors. Hence the discussion about the water acting as a moderator.
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@JM
I think you are missing the point about how moderation works.
Some background material here:
http://en.wikipedia.org/wiki/Neutron_moderator
Inserting control rods stops the reactor by displacing the moderator – that is, by removing the water between the fuel rods. The water _is_ the moderator. The control rods are _not_ the moderator.
The counter intuitive thing about nuclear reactions in this kind of reactor is that they rely on slow neutrons whose speed has been moderated by interaction with H2O. This differs from fast reactors where fission relies on fast neutrons.
I think if you take the time to understand how neutron moderation works, you might not be so mystified by the points being made here.
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The National Academy of Sciences in the US was asked to consider what can happen to a spent fuel pool after the terrorist attacks of 9/11. The sections that were not classified material were published as
Safety and Security of Commercial Spent Nuclear Fuel Storage.
The report discusses cheery topics such as propagating zirconium cladding fires and the possibility of the rods becoming critical.
You want to keep it firmly in your mind if you read this thing that the panel clearly stated no one asked them to rank the threats they discuss compared to anything, i.e. the rest of what could happen in the US as a result of terrorist attack. They were charged with considering “what if” and that’s what they did.
Although they said: “Additional analyses are needed to understand more fully the vulnerabilities and consequences of events that could lead to propagating zirconium cladding fires”, they could not “dismiss” the possibilty and recommended rearranging spent rods in the pools and adding water spray systems that could cool the rods even if “the pool or overlying building were severely damaged”, by terrorist attack.
They did sort of dismiss one theoretical possibility: “The committee could probably design configurations in which fuel might be deformed or relocated to enable its recriticality, but the committee judges such an event to be unlikely”.
I discussed spent fuel pools in this TEC post.. It proved to be very controversial which is apparent from the debate in the comments and the stature of the pro nuclear advocates who engaged.
BTW, Eastern Washington state is often mentioned when the subject of relatively high background radiation levels comes up. Spokane, a small city out east is said to have 5 times the level normally found in Seattle. My impression is its above 1500 rem/yr.
People from Denver have to come up here if they find they aren’t glowing the dark strongly enough.
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Jon Seymore, I think you need to read your own reference:
. Therefore, neutrons are more rapidly moderatedJ by light water,
It then goes on a couple of sentences later to discuss the advantages of heavy water, but “light” aka ordinary water is definitely a moderator.
You don’t know what you’re talking about. The behaviour of atoms and molecules isn’t changed (much) just because the atomic weight changes.
And if you think you do, can you explain to me why you think a dry saucepan left on your stove won’t burn?
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The Energy Collective has stated that they are refusing to post my pieces which quote the current thoughts of Ted Rockwell, who is closely monitoring reports from Japan.
Their first attempt at an excuse is to explain that it is redundant to hear what someone like Ted has to say in the light of what’s happening at Fukushima because they’ve already published my piece quoting Ted from a Science article he wrote in 2002.
No one could possibly be interested, they are pretending, in the thoughts of someone who was the Technical Director of the program that built the first commercial nuclear reactor in the world, about how great a threat the reactor problem in Japan can evolve to be.
Just to illustrate my point that it is getting very weird out there.
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David, don’t worry, I shall post it in the morning.
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David Lewis wrote,
> Spokane, a small city out east is said to have 5 times the level normally found in Seattle. My impression is its above 1500 rem/yr.
above 1500 millirem/yr perhaps?
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Sea water is pumped into the pressure vessel (as well as into the first containment).
See reactor status at http://www.jaif.or.jp/english/
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@JM – good grief! where on earth did you learn nuclear physics, or thermodynamics for that matter?
A possible explanation for the generation of hydrogen in the SFP.
The water temperature is normally 25C. Cooling will take place by natural convection under normal circumstances. if the temperature rises to 84C natural convection is not that effective. you may get film boiling on the zircalloy tube surface. local surface temperatures may rises sufficiently to cause oxidation of the zircalloy and consequent generation of hydrogen. You can eventually burn/fuse the element in your kettle in this way?
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“It seems to me to be very unlikely that the water levels in the spent fuel pools (SFPs) could have been greatly lowered by evaporation and boil-off, since the pumps stopped circulating the water on 3/11/11. Luke’s heat-generation calculations seem to indicate that. (Luke, has your view changed?)”
You might like to see the other comment I recently posted on Barry’s other thread above, regarding evaporation/boil rate in the pool.
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Here’s a scary picture:
http://www.china.org.cn/china/national/2008-09/09/content_16415475.htm
Hat tip to: https://bravenewclimate.com/2010/06/18/21c-nuclear-renaissance/
More info:
http://tidesandcurrents.noaa.gov/press/update031111.shtml
“The first waves hit the coast of Japan within minutes, with visual reports of 23 foot waves. The largest official recorded tsunami amplitude was at Hanasaki, Hokkaido, Japan, with a height of 1.83 meters (6.00 feet) at 0656 UTC (0146 EST). It is important to note the amplitudes are reported as height of the peak above “normal sea level,” rather than a peak-to-trough measurement. This means that the observed wave (a tsunami is typically a series of waves, rather than a single wave), or increase in water level, is actually typically twice this number.”
But when you look at the videos you see water levels on buildings much higher than six feet above the ground around the building. How well do designs capture the observed behavior of the ocean?
Does anyone know the tide level at the time the tsunami hit Japan? on the west coast of N. America the tsunami hit at low tide — the people at the affected ports were quoted as saying the water would have been six feet higher at ‘high high’ tide.
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Hank Roberts,
There seems to be something strange about the way people are writing about tsunami preparedness. Ian Hore-Lacy, a spokesman for theWorld Nuclear Association, was quoted by Bloomberg saying, “Japanese authorities designed backup electrical generators to withstand waves 6.3 meters high, below the 7-meter surge that knocked out power at the [Fukushima] plant, disabling vital cooling systems.”
This seems quite inconsistent with the before-and-after satellite images of the complex. The tsunami swept away the backup generators, tanks, small outbuildings, cars, and equipment. It reached well inland from the reactor buildings themselves, and flooded their basements. It apparently fouled many of the plant’s intakes.
I find it hard to understand how a sea level rise that is 70 centimeters higher than the design criteria could accomplish all that destruction.
Were the waves and sea level rise at this location much higher than the 7 meters cited here?
Or, did the “designed to 6.3 meters” claim refer to something non-obvious, e.g. “a 6.3 meter tsunami that arrives at low tide”?
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JM, you are confused about what a neutron moderator does in a nuclear chain reaction. Fast neutrons (no moderator) means the neutrons (mostly) escape the reactor vessel without hitting any (many) fissionable atoms and the reaction slows and stops.
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Hank, if you read the article it says they are looking for an inland site for that plant.
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Seamus, that picture is of a new reactor already being built, on the coast. It’s due to start up soon. You can search using the text right out of the article about it, here:
http://www.google.com/search?q=Sanmen+Nuclear+Power+Project+(NPP)+in+Zhejiang+Province
The site selection criteria for coastal, freshwater shoreline and inland sites are discussed, including concerns about having enough cooling water, enough external power, and where the waste water goes — one of the links will get you to this:
Click to access China_FengleiDu.pdf
My concern is — are these kinds of decisions on these coastal sites being made by the same people who flat out refuse to consider the “worst case” projections we have for sea level rise?
“Cromwell’s rule, named by statistician Dennis Lindley, states that one should avoid using prior probabilities of 0 or 1 …”
http://en.wikipedia.org/wiki/Cromwell%27s_rule
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Very close to the Fukushima Daiichi site, one website has the tides for Friday March 11 at Ottozawa, Fukusima (sic) as:
2011-03-11 06:45 JST 1.30 meters High Tide
2011-03-11 14:10 JST 0.24 meters Low Tide
2011-03-11 21:02 JST 0.89 meters High Tide
The quake struck at 14:46 JST. IEEE Spectrum’s timeline says the generators failed at 5:41 JST.
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> The quake struck at 14:46 JST. IEEE Spectrum’s
> timeline says the generators failed at 5:41 JST.
Hm, other reports say the tsunami came an hour after the quake and the pumps stopped then, with loss of outside power, and the generators failed after that. I’d bet “5:41” is a typo. Any other cite?
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Typo … IEEE Spectrum’s timeline says the generators failed at 15:41 JST.
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> 70 centimeters higher than the design criteria
Dunno. I’d guess that means the waves came over the sea wall; once that happens a seawall is a liability if it survives, because it keeps the water from running back out. And there are multiple waves, not just one.
—-
> Unit 4
http://www.world-nuclear-news.org/RS_Attempts_to_refill_fuel_ponds_1703111.html
“… In the previous two days the temperature of unit 4’s pond had been 84ºC but no more recent data is available. At these temperatures cooling by natural convection begins to be markedly less effective. Normal operating levels are about 25ºC. There was no information on the temperature of the pond at unit 3.
However, the high levels of radiation and presence of hydrogen at unit 4 strongly indicate that fuel is uncovered and suffering damage in the pond, although it was not clear that the pond actually emptied. Officials were reassured the pond contained at least some water, based on helicopter observations.”
———
Anyone know more about the actual temperature measurements? Location of sensor(s); whether we’re getting an average of readings taken at intervals over time?
If a sensor is above water level, it’s getting an air temperature rather than a water temp., and the outside air in the area is around freezing — it’s been snowing, and there’s some wind blowing through, as the photographs of steam coming out of Unit 4 show.
A steam cloud in cold air necessarily mean the water is at boiling temperature, which gives some hope yet.
If the outside temperature drops below freezing, the air will be dryer as water freezes out, enhancing evaporation from the pools.
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wups —
make that
“A steam cloud in cold air _does_not_ necessarily mean the water is at boiling temperature, which gives some hope yet that the reported readings from previous days are accurate.”
I wonder if a crane could get close enough with an infrared thermometer to get temperature readings. Or one of those little remote control helicopters used to carry in a thermometer — if anyone has such that can stand the radiation environment.
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> waves came over the seawall;
Remembering this is a “tidal wave” — prolonged, like a high tide event not a high wave like from a storm — the water stays high for a long while and would continue to pour in. Well we’ve all seen videos by now of that happening. So a “70cm” water height above design criterion is a complete failure.
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Alas — revisiting the Gen2 design criteria _is_ needed!
http://www.world-nuclear.org/info/inf63.html
Nuclear Power in China
(Updated 10 March 2011)
“… In January 2011 a report from the State Council Research Office (SCRO), which makes independent policy recommendations to the State Council on strategic matters … cautioned concerning provincial and corporate enthusiasm for new nuclear power plants and said that the 2020 target should be restricted to 70 GWe of new plant actually operating so as to avoid placing undue demand on quality control issues in the supply chain. Another 30 GWe could be under construction.
… ambitious targets to deploy AP1000s with reduced foreign input had proved difficult, and as a result, more of the Generation-II CPR-1000 units are under construction or on order.
Only China is building Gen-II units today in such large numbers, with 57 (53.14 GWe) on the books4.
SCRO said that reactors built today should operate for 50 or 60 years, meaning a large fleet of Gen-II units will still be in operation into the 2070s, when even Gen-III reactors would have given way to Generation-IV and perhaps even to commercial nuclear fusion. …”
———-
Seeing official acknowledgment about ” placing undue demand on quality control issues in the supply chain” is somewhere between eye-opening and hair-raising, given this is China, a government operation, and the ongoing series of reports about disclosure of failure of quality control on, for example, big concrete construction projects that have collapsed.
Make that hair-raising for sure:
http://www.chinalawblog.com/2007/07/china_products_its_always_dark.html
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I often remark that many American nuclear regulatory personnel are on-site, as they should be for all large energy facilities that are more likely to do harm if the regulators don’t care.
But I know nothing about whether this wise arrangement exists in other countries, even my own.
So, does it? In Japan, in Canada, or in any nuclear power country for which you happen to have that knowledge?
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Ok Hank, fair enough. I don’t really like any kind of PWR in any case. The AP1000 claims to have a lot of passive safety features, but they look pretty complex. I like the simplicity of the liquid sodium IFR. Linked to an article about it halfway up this thread.
The problem as I see it is not tsunamis. It’s the need to provide active cooling. There are all sorts of situations where the pumps might stop for some reason. So let’s skip Gen III and build Gen IV.
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> So a “70cm” water height above design criterion is a complete failure.
I suspect the gap between the actual tsunami-resistance capacity of the Fukushima complex (as it stood on 11 March) and the actual height of the tsunami was much more than 70 cm.
From the look of the satellite pictures, this tsunami would have been disastrous for operations, even if it had been a meter lower. Two meters? Lower still?
The force of the rushing water around the reactor buildings was obviously great, considering the damage it did. And it didn’t stop one critical aspect of plant operations, but multiple elements.
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yes yes millirem. Some prospecting for uranium has been done in the region, a bit north of Spokane ijust across the border in Canada where at the surface there are far higher readings, according to a prospector I met. The Canadian provincial jurisdiction controlling whatever is there put a moratorium on uranium prospecting some decades ago as they have very large hydroelectric resources.
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@JM
“So am I to understand that you stop the reaction in a reactor by removing the cooling rods????”
There is no such a thing as a cooling rod. There are fuel rods and control rods. The cooling does not come from any sort of rods. Neutron moderation may, in principle, come from some sort of rods (graphite tips in Chernobyl control rods had this effect when they became stuck), but in BWR reactors both cooling and neutron moderation is provided by water.
“That in an earthquake you should lift the rods out of the reactor rather than drop them in?”
You drop in the control rods. This shuts down the reaction by removing most of the neutron moderation provided by water and, on top of that, absorbing fast neutrons (the control rods are neutron absorbers, not neutron moderators).
“For another perspective consider this:
– why are these rods put in water in the first place?”
Are you talking of the fuel rods in the working reactor core, a shut down reactor or the spent fuel rods in the pool?
For those in the working reactor the main reasons are:
– the whole point of the reactor is to generate steam pressure to drive the turbines
– water is a neutron moderator and therefore enhances the chain reaction, without the moderation the chain reaction would slow down or even stop
For those in a shut down reactor or in the pool the main reasons are:
– water acts as a coolant, you need to cool the fuel rods to prevent damage (zircaloy oxidation or melting depending on temperatures).
– water acts as a shield to radiation (especially important in the pools, less so in the reactor).
“- why does it become so dangerous to go near them if there is no water?”
Because they are highly radioactive.
What you really seem not to understand is that water is a proton moderator when there is a chain reaction. If the chain reaction is stopped there is no proton moderation whatsoever and water is just a coolant and radiation shield.
Radiation from fission products decay is mostly alfa, beta and gamma. In the pools water acts as a shield for these (as well as being a coolant). There is no proton moderation here.
The original comment by fp was
“fp: With the water moderator gone, the reaction (if any) will slow down if anything.”
Which is correct. There is no chain reaction, but if the fuel rods were to go critical (for some inexplicable reason) the absence of water would in fact slow down the reaction (actually I believe almost stop it, in comparison to the levels of a working core, even if the rods were not spent fuel but new ones).
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@JM
You still seem to misunderstand the term “moderation”.
Water has two different effects within a reactor core: one is thermal, one is nuclear.
The thermal effects of water do transfer heat from the core, such as water in a pot transfers heat from the stove.
On the other hand, water also has nuclear effects. It affects the fission process by slowing down the neutrons and making fission more likely. The presence of any kind of moderator, water or otherwise, will cause the fission process to release more heat than it would otherwise.
The term “moderation” does not refer to the thermal effects of water removing heat from a hot core. It does refer to the nuclear effects of slowing down neutrons. By enhancing fission, this has the effect of heating up the core, but only if a fissioning process is under way.
So a more effective “moderator” will cause a fission process to be more effective and therefore release more heat.
You really need to understand that “moderation” is refering to the nuclear effects of water and not the thermal cooling effects and that these two effects are quite different.
[ad hom deleted]
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Can anyone point me to an explanation about why the material released from molten fuel rods cannot go critical?
Yes, fission of a contiguous mass will be less effective than fission of discrete masses moderated by water, but what actually prevents criticality being achieved anyway?
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Jon, the cross-section of the fissile material (the ‘area’ the neutrons have to hit) is greatly reduced in the absence of water (since the neutrons are fast), and the neutron loss is very high in a low-enriched, ungeometric situation like this, such that a sustained chain reaction is impossible (more neutrons are lost than are regenerated via fission).
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Barry,
I think I understand how this occurs – slower neutrons have more targets to hit. In a normal fuel assembly what factor does the presence of water increase th e cross-section by?
Could abnormally high volumes of material that have pooled together increase the effective cross-section or do 3D packing considerations mean this isn’t a problem for realistic contiguous masses?
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G.R.L. Cowan,
I can tell you that here in Spain there are at least two resident inspectors from the CSN (Spanish Nuclear Security Commission) in every nuclear power plant.
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Fukushima 1 was built just one decade after the 9.5 magnitude Valdivia earthquake, which caused tsunamis over 25 metres. These tsunamis reached Japan at the time. Yet they only designed the Fukushima facility for a much, much lower 8.2 magnitude earthquake rating.
Why could they not even design this plant to meet an earthquake/tsunami scenario that had occurred just a few years previously? Why did they design such appallingly inadequate contingency cooling systems in the face of this scenario?
If it wasn’t cost, what other reasons? Blind optimism? Over arrogance in the face of prudent risk analysis? Lack of humility to the possibility of failure, perhaps ? An inability to take on constructive criticism?
[unsubstantiated personal opinion deleted]
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Barry: such that a sustained chain reaction is impossible
You are talking nonsense. Have you heard of nuclear bombs? I wasn’t aware they needed water – or indeed any form of moderation – to achieve criticality.
In any case, the major risk with a meltdown is a steam explosion if the molten fuel hits the water table. (And that’s aside from the more minor issue of radioactive material burning in an uncontrollable fire)
sunake: where on earth did you learn nuclear physics, or thermodynamics for that matter
At the School of Physics for a major university, where did you learn yours?
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JM – if you don’t have a moderator, you must have a much higher % of fissile material. Oh, and stop with the ad homs or you will be put on moderation.
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This discusses _transport_ of assemblies of spent fuel rods — and the sort of considerations used to model and assess the chance that a transportation accident and/or fire will lead to a critical assembly (and thus, what to avoid in packing the stuff up to put it on the road).
These folks sure do have a lot to think about. It ain’t simple.
Nuclear Engineering Magazine
http://www.neimagazine.com/story.asp?sc=2059050
“Imparting realism to criticality evaluations 04 March 2011
The most reactive configuration for the fuel assembly contents of a BWR package must take into consideration parameters that may not be known with a high degree of certainty, such as burnable absorber rod distribution and packaging material composition during a fire….”
Want something to worry about?
How about known sites that _do_ have much higher percentages of fissile material they’re working on dealing with:
http://www.springerlink.com/content/ur2866117n025q32
http://www.bellona.org/articles/articles_2010/Russia_%20Atomflot_%20reports
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> let’s skip Gen III and build Gen IV.
Yep. I suggested a year or two ago that IFR should stand for Improved Fissionables Reduction — sell them as a way to burn up the piles of ‘used’ fuel. Set’em up next to coal boilers and eventually switch to them as an alternative heat source. They’ve already got the railroads, the huge yards to store material, the generators — just replace the coal burner with a relatively small Gen IV heat source.
Give the coal companies money for the amount of radioactive fly ash they will no longer be putting into the air and the waste piles– buy’em out as an explicit way to end the biggest source of heavy metal and radioactive material going into the environment “grandfathered” right now.
Mine the fly ash for its fissionables.
http://www.scientificamerican.com/article.cfm?id=coal-ash-is-more-radioactive-than-nuclear-waste
Instead of deregulating fission, bring the fossil fuel sources up to the same level of care.
And do the research comparing health effects properly.
As they say about carbon dioxide, if it turns out later on that we actually need more of it in our environment, that’s easy to make happen. But if it turns out we do have enough already, or too much, we’ll be glad we throttled it sooner than later.
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re post by: Hank Roberts, on 20 March 2011 at 7:12 AM
Hank, spent fuel both commercial and military, along with weapons grade material, has been transported all over this nation and Russia/USSR for many decades now. Why in the world are you providing links to the Russian ships where it’s not even reporting problems with handling the nuclear material, but with red tape and even not having as many cranes available so they can offload faster? And then a hypothetical plume travel bit of research that doesn’t even say if there is a mechanism to get the release they’ve used to run their computer model? And you present this as something to be really afraid of? Come on man, get real.
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Yes Barry that is true, but fast neutrons can still cause fission which is quite opposite to the statements you were making.
And what ad homs? sunake had a go at me, I replied – politely I think.
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> And what ad homs?
How about this:
> You don’t know what you’re talking about.
Or this:
> You are talking nonsense.
jon.
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Yes Barry that is true, but fast neutrons can still cause fission which is quite opposite to the statements you were making.
Fissionable nuclei look a lot smaller to fast neutrons than fissile nuclei do to thermal neutrons. This means a fast neutron has to travel much further to encounter an opportunity to split a fissionable nucleus.
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Yes, I know that Finrod, it’s the definition of cross section.
But a point and a question. First you are confusing (I think) the neutron capture cross section and the total fission cross section.
Second a question: What do you think is happening in a fast reactor, which by definition is unmoderated?
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Jon How about this:
The first one was in response to someone who claimed water was not a moderator, but now I’m being berated by all and sundry for a.) pointing out that it is (and is in fact used as such in BWR like those at Fukushima) and at the same time being told that I’m “wrong” in some totally undefined way while people also accept my point.
The second one was in response to Barry’s use of the term “cross section” (which in my view he doesn’t understand) to claim that fusion was impossible without a moderator. Which is something he’s definitely wrong about.
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@JM:
Yes, I know that Finrod, it’s the definition of cross section.
You don’t seem to appreciate the implications.
But a point and a question. First you are confusing (I think) the neutron capture cross section and the total fission cross section.
Nope.
Second a question: What do you think is happening in a fast reactor, which by definition is unmoderated?
I believe that fast neutrons are collising with fissile and fissionable nuclei and fissioning them to produce great amounts if heat and new liberated neutrons. I also understand that the process requires a much greater amount of fuel than is found in a light water reactor, because of the issue I mentioned above about the much longer travel path of the neutrons before a likely collision. And the presence of anything significant in the way of light elements will moderate the neutrons enough to stop the reaction.
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Jose A says,
Thank you.
(How fire can be domesticated)
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@JM
> The first one was in response to someone who claimed water was not a moderator
Wrong, If you read that response carefully you will read that I stated water was a moderator. I wrote in fact,
“The water _is_ the moderator”
I only wrote this because you seemed to be very confused about how moderators work in BWR reactiions, In particular, it seemed that you believed that moderattors acted to slow down the fission reaction when, in fact, they do the reverse,
For example, you wrote:
“Yes. You know nothing about nuclear reactions or power. Your own sentence explains it – “moderator” means to slow down. “accelerator” is the word you need for your argument to make sense.”
Yes, they slow down neutrons, but that actually acts to enhance the fission reaction, not slow it down.
jon.
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Finrod: You don’t seem to appreciate the implications.
Why not? I think I do actually, but perhaps if you could be a little more forthcoming about your concerns I can address them.
Nope
Same as above, more detail please.
[noise]
We’re not talking about a light water reactor. We’re talking about a storage pond where there is no cooling, fires have occurred , there is a possibility of meltdown and whether or not development of a criticality in such a situation is possible.
I, and many other people – including TEPCO and the Japanese government – are worried about this.
It’s up to you to explain why you are not.
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@JM:
We’re not talking about a light water reactor. We’re talking about a storage pond where there is no cooling, fires have occurred , there is a possibility of meltdown and whether or not development of a criticality in such a situation is possible.
You do seem to be awfully confused even about the details of the exchange that has occured between us. You didn’t ask me anything about light water reactors or spent fuel ponds. You asked me a question specifically about fast reactors, and you were answered. When you did not like the answer, you airily dismissed it as ‘noise’.
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> [noise]
For the life of me, I cannot see how dismissing another’s explanation as ‘[noise]’ can be regarded as civil behaviour.
It is just plain rude.
jon.
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Fin, your comment was noise. If you take something like a molten pool of metal then it is the most undesigned thing that I can think of.
And getting a criticallity in it is not impossible. There is a large amount of material in a reactor core – well beyond what is required for criticality and there are reports that the storage pond in Reactor 4 contains about 7 cores worth.
There’s no shortage of material in other words and arguments based on the efficiency of the process are worthless.
That’s what we’re talking about here.
(And I didn’t pick you up on this before because I didn’t think it was worth it, but maybe it is:- a cross section is not an area, but it can be visualized like that and it is common to do so because it evokes a classical analogue and it brings physical intuition to your aide. A cross section is a probability.)
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What JM is claiming:
Fin, your comment was noise.
What JM originally asked me:
Second a question: What do you think is happening in a fast reactor, which by definition is unmoderated?
The answer I gave in response to the above question:
I believe that fast neutrons are collising with fissile and fissionable nuclei and fissioning them to produce great amounts if heat and new liberated neutrons. I also understand that the process requires a much greater amount of fuel than is found in a light water reactor, because of the issue I mentioned above about the much longer travel path of the neutrons before a likely collision. And the presence of anything significant in the way of light elements will moderate the neutrons enough to stop the reaction.
It’s possible to claim all sorts of things about another’s comments if you completely ignore the actual content.
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@JM – Let me put this to rest. Fission can occur in reactors without a moderator, it is true. HOWEVER the relative concentration of rich fissile material is very much higher when compared to that required for a thermal reactor. This being the case it can be asserted correctly that no fission will occur when the moderator is lost from the core of a thermal reactor because the enrichment of the fuel will not support it, and note that this must hold true for spent fuel pools for the same reason. Even in a full meltdown, the relative concentration of fissile material does not change, thus there is no risk of continued fission in this case ether.
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DV8XL I disagree.
DV8XL: because the enrichment of the fuel will not support it,
This is in total contradiction of earlier comments on this thread about the profile of the cross-section of U235 and U238 with respect to neutron energy.
If we’re talking only about U238 then fission will only occur in a restricted band (but not particularly limited), however if it is enriched with U235 it will occur over a much wider band of neutron energies. This is a well established fact.
and note that this must hold true for spent fuel pools for the same reason
This statement is nonsense. It is tantamount to saying that either cooling ponds have no purpose or that they are themselves reactors.
What is your preference?
there is no risk of continued fission in this case ether
Rubbish. There is plenty of risk of fission in a meltdown, as well as the more subordinate risks of fire (which has already occurred) and steam explosions.
Don’t talk nonsense.
[deleted personal opinion presented as fact. Please re-post with references]
I think they know what they are doing, and the implications. The opinions of people on this blog don’t matter a hill of beans to those people.
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@JM – I no longer care if you agree or disagree, because it is clear you have no real understanding of the underlying physics, and obstreperously refuse to squire the background to do so. At any rate the rules of the game in science is to prove any hypothesis you are asserting, not demand that others prove you wrong.
Therefore I invite you to prove your thesis with the applicable calculations, posted so that we can all see your reasoning. That or stand down as an ignoramus running off at the mouth about something they know nothing about.
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Jon, I did actually respond to your comment a couple of hours ago. I was quite respectful – I think – but it seems to have disappeared. I don’t know why.
In fact, some of the latter part of this thread seems to be missing (yes Barry, I do keep copies of this stuff).
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Off-topic comments have been deleted, as per Commenting Rules. Please re-post to the new Fukushima Open Thread
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DV82XL, I have no intention of posting calculations because I don’t have the data and as far as I’m aware TEPCO are pretty secretive. And in anycase it’s not the way physics is conducted.
But the fact is that a cross section is a probability that is mathematically structured in a convenient way to represent the probability of some result happening in a sub-atomic event.
It just so happens that when you structure it that way it has the dimensions of an area. That is a classical analogue. It doesn’t actually mean that – contrary Finrod – the target is smaller or larger physically, it just gives you a convenient way to think about it.
Now one of the problems that’s happened on this thread is that a number of people think that a cross-section is
a.) a real physical thing where the particles act like billiard balls ie. in a classical manner exactly equivalent to the physical analog implied by the cross-section
b.) that the restricted model applicable to a thermal reactor is also applicable to all atomic events – it is not.
Ok?
Now if you disagree you can explain to me
i.) why a meltdown can never occur
ii.) why a meltdown cannot ever lead to a criticality
I think you should – when preparing this explanation – be aware that just every responsible agency in the rest of the world think that both of these things are possible in the current circumstances (or at least in the recent past)
Please. I await your reply.
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@JM – First you don’t need data from this event, the general case will do, and the levels of enrichment both in fuel, and in typical spent fuel are well documented. The fact is you cannot because you don’t know how, and obviously don’t know where to start.
Again, if you contend that fission can occur in the core of a typical thermal neutron reactor, you should be able to show calculations supporting this hypothesis. If you cannot it is not up to anyone else to prove you wrong. Your demands clearly show that this idea is the product of your imagination, and is founded on a profound ignorance of the physics involved.
Furthermore paragraphs 2 through 6 are pure rubbish. This might impress others that have no real knowledge of nuclear physics, but to those that do, [ad hom deleted]
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if you contend that fission can occur in the core of a typical thermal neutron reactor
Ahh. This is not the 1920’s. There are quite a number of commercial reactors around the world doing that right now, as we speak.
I don’t have to prove a damn thing, I can simply point to existent implementations of the technology.
paragraphs 2 through 6 are pure rubbish
Fine, if you think that I am more than open to the idea that I may be wrong. But abuse like that in your following sentence doesn’t cut it.
Explain why.
MODERATOR
Abuse has been deleted.
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@jm – Correction the line should have read: Again, if you contend that fission can occur in the core of a typical thermal neutron reactor, without the moderator you should be able to show calculations supporting this hypothesis.
Writing the truth is not abuse. Your statements are nonsense, and demonstrate a total lack of understanding.
[ Ad hom deleted]I have explained that the conditions favoring fast neutron fission do not exist because the concentration of fissile material is just not there in the fuel of thermal neutron type reactors. It is just that simple.
Now if you can show it is possible by presenting a calculation based argument, I will gladly admit you are right. But we both know you cannot.
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JM is on permanent moderation after his latest comment (deleted) which violated about 3 different commenting rules. I don’t think he really wants to be here, which is fine. There are plenty of other commenting playgrounds on the Internet.
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Noting belatedly an error above; Luke Weston wrote:
“HPCI is driven by steam … but it can only be operated for a limited amount of time following shutdown, because the decay heat power output isn’t enough to raise enough steam.”
That’s wrong; the decay heat doesn’t drop off nearly that fast, the reactor vessel stays hot much longer.
The steam pump works (for a while) by condensing the steam into the cooler water and pushing that cooler water up into the core. Eventually the torus water gets so hot it boils and with no relatively cool water to push up, the pumping action stops.
————-
So what’s “corium” exactly? Does it mean whatever’s in the fuel? For unit 3, not just uranium as mentioned above but also plutonium, right?
Term used several places:
http://www.google.com/search?q=site%3Abravenewclimate.com+corium
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Hank,
I also saw the term corium used in one of the papers you have listed here recently, though I can’t remember which one.
As I understand the term, it is the substance that results from a meltdown, so it is fuel, control rods, bits of pressure vessel and anything else that it comes in contact with.
Not nearly as scholarly as your references, but not a bad place to start…
http://en.wikipedia.org/wiki/Corium_(nuclear_reactor)
jon,
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