Japan Earthquake: Nuclear Plants at Fukushima Daiichi

AI Thread Summary
The Fukushima Daiichi nuclear plant is facing significant challenges following the earthquake, with reports indicating that reactor pressure has reached dangerous levels, potentially 2.1 times capacity. TEPCO has lost control of pressure at a second unit, raising concerns about safety and management accountability. The reactor is currently off but continues to produce decay heat, necessitating cooling to prevent a meltdown. There are conflicting reports about an explosion, with indications that it may have originated from a buildup of hydrogen around the containment vessel. The situation remains serious, and TEPCO plans to flood the containment vessel with seawater as a cooling measure.
  • #11,601
http://www.meti.go.jp/press/2011/11/20111104007/20111104007-2.pdf Report from Tepco to NISA about the xenon detection. (4 November 2011, Japanese, 18 pages)
 
Last edited by a moderator:
Engineering news on Phys.org
  • #11,602
Last edited by a moderator:
  • #11,603
thebluestligh said:
Thanks Tsutsuji as always, I found a report from TEPCO in English version as well

http://www.tepco.co.jp/en/press/corp-com/release/betu11_e/images/111104e19.pdf

If I understood the TEPCO report correctly, they have

(a) completely neglected the subcritical multiplication, justifying this by conservativity
(b) assumed all Xe-135 created by SF is immediately released in the containment airspace, which I think is a huge error in the non-conservative direction, since the cool fuel/corium should certainly be able to contain a significant amount of the fission products

Did I miss something? Can someone make better sense of the report?
 
Last edited by a moderator:
  • #11,604
rmattila said:
If I understood the TEPCO report correctly, they have

(a) completely neglected the subcritical multiplication, justifying this by conservativity
(b) assumed all Xe-135 created by SF is immediately released in the containment airspace, which I think is a huge error in the non-conservative direction, since the cool fuel/corium should certainly be able to contain a significant amount of the fission products

Did I miss something? Can someone make better sense of the report?

I'm more interested in why they keep harping on about Curium. It's certainly not the only fissile in there.

To your first question: it is strange indeed.
As to your second question, they are probably assuming that the corium is saturated, so naturally all excess production goes into the containment immediately.
 
Last edited:
  • #11,605
thebluestligh said:
Thanks Tsutsuji as always, I found a report from TEPCO in English version as well

http://www.tepco.co.jp/en/press/corp-com/release/betu11_e/images/111104e19.pdf

Thanks for the English version.

The following translation, while not wrong, was forgetting to mention that the ratio is found using the krypton 85 measurements:
Collection efficiency of the charcoal filter is 1566 times as determined from the ratio of the values of Kr-85 measured in the charcoal (5.3E-1 Bq/cc) and [STRIKE]the value measured[/STRIKE] in a vial (8.3E2 Bq/cc).
 
Last edited by a moderator:
  • #11,606
The following is from
http://www.tepco.co.jp/en/press/corp-com/release/betu11_e/images/111104e19.pdf

If the Unit 2 fuel is in the critical state, Xe135 concentration is observed 4 orders of magnitude larger than current level. Therefore, present state is not considered critical.

OK, so on Aug 9 they found Xe-131m at 3.8 X 10¹ to 4.7 X 10¹ Bq/cm3 in the lower floors of Unit 2. This is 5 orders of magnitude greater. According to Tepco's analysis criticality has occurred. Am I missing something?
 
Last edited by a moderator:
  • #11,607
dezzert said:
Am I missing something?

The contribution of the residual I-131 (remaining in the containment water since March) on the Xe-131m production.
 
  • #11,608
Via http://ex-skf.blogspot.com/2011/11/xenon-detection-in-reactor-2-different.html" :

Comparison between the three gas tests on October 28th, November 1st and November 2nd. Looks quite funny. With the detection limits being very funny.

fukushimareactor2xenontable.JPG


So... what the heck? No wonder they didn't detect any Xenon on October 28th.
 
Last edited by a moderator:
  • #11,609
rmattila said:
The contribution of the residual I-131 (remaining in the containment water since March) on the Xe-131m production.

Thanks rmattila. Woudlnt the residual I-131 be gone by then. And certainly not in numbers to produce those levels of Xe-131m.
 
  • #11,610
rmattila said:
Is it really so? In my reference inventory, the alpha activity of Pu-238 is about 5 times larger than that of Pu-240, but its SF probability is so much lower (1,8e-9 vs. 5,5e-8) that the SF rate would actually seem to end up lower by a factor of 5 (9e6 vs. 5e7):


[nuclide] [Bq] [T12] [T12(s)] [SF T12] [SF t12(s)] [SF prob.] [nu] [SF rate] [SF neutron production]
Pu-238 5,00E+15 87,7a 2765707200 4,90E+10 1,55E+18 1,79E-09 2,2 8,95E+06 1,97E+07
Pu-240 9,00E+14 6550a 2,06561E+11 1,20E+11 3,78E+18 5,46E-08 2,2 4,91E+07 1,08E+08
Cm-242 3,00E+16 162,8d 14065920 7,20E+06 2,27E+14 6,19E-08 3 1,86E+09 5,58E+09
Cm-244 4,00E+15 18,11a 571116960 1,40E+07 4,42E+14 1,29E-06 2,8 5,17E+09 1,45E+10

Even though the conclusion is the same, it would be nice to know where and why our results differ in this respect.


I am using a different source term list from a US BWR4 and the fission branch percentage and isotopic yields I used from an old textbook. The textbook data includes data uncertainty ranges which I used to produce conservative (low) results. I used the same source term and updated values for fission branch and yield from http://atom.kaeri.re.kr/index.html and now Pu-240 is about 4 times larger than Pu-238. Since the data I got online has no uncertainty data I classify the new results as a best estimate case.

My analysis included 4 Uranium isotopes, 1 neptunium isotope, 6 Plutonium isotpes, 3 americium isotopes, and 5 curium isotopes that can spontaneous fission. All of my results are well within one order of magnitude of yours which is what I believe is reasonable agreement based on different data and the uncertainty of that data. Switching to the new values did not change that result, because the effects of curium seem to control the data.

Other than that I made several assumptions and some additional data:

  • I developed and solved a linear first order differential equation based on fission and spontaneous fission sources and removal by decay and leakage. It demonstrated that the isotopes of concern are appropriately treated as equilibrium values due to the long half lives of the fission sources.
  • I assumed that the relative sources for spontaneous fission
  • My inventory lists 50 transuranic and actinide isotopes and is based on a typical equilibrium core. Japanese operating cycles are probably shorter and so transuranic sources may be overestimated.
  • I assumed a single fission product yield curve for U-235.
  • I assumed a single value for neutron yield from fission.
  • I assumed zero out-eakage, but ran cases for 5, 10, and 20% keakage rates.
  • I included cases for Keff and subcritical multiplication from 0.7 t0 0.999. I used the results for Keff -0.8 for consistency.
  • I included release of Xe from I Beta decay.
  • I used a smaller free volume for containment to account for a water level inside containment.
  • I uswd source terms based on 8 months decay and buildup.
 
Last edited:
  • #11,611
I did not have a suitable BWR inventory right at hand and no time to calculate one either, so I had to do with a VVER EOC inventory and scale it according to the thermal power level. Using an EOC inventory, I probably overestimated the transuranics, thus I believe your results to be better than the quick sketch I made in order to have at least something to base the estimates on.
 
  • #11,612
dezzert said:
The following is from
http://www.tepco.co.jp/en/press/corp-com/release/betu11_e/images/111104e19.pdf

If the Unit 2 fuel is in the critical state, Xe135 concentration is observed 4 orders of magnitude larger than current level. Therefore, present state is not considered critical.

OK, so on Aug 9 they found Xe-131m at 3.8 X 10¹ to 4.7 X 10¹ Bq/cm3 in the lower floors of Unit 2. This is 5 orders of magnitude greater. According to Tepco's analysis criticality has occurred. Am I missing something?

clancy688 said:
Via http://ex-skf.blogspot.com/2011/11/xenon-detection-in-reactor-2-different.html" :

Comparison between the three gas tests on October 28th, November 1st and November 2nd. Looks quite funny. With the detection limits being very funny.


fukushimareactor2xenontable.JPG


So... what the heck? No wonder they didn't detect any Xenon on October 28th.

clancy 688 - what are the units of those measurements? dezzerts values (Bq/cm^3) from Unit 2 are significantly different.
 
Last edited by a moderator:
  • #11,613
NUCENG said:
clancy 688 - what are the units of those measurements? dezzerts values (Bq/cm^3) from Unit 2 are significantly different.

Sorry, but what do you mean?

All of these values have the unit of Bq/cm³. http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111102_04-e.pdf" the original.
 
Last edited by a moderator:
  • #11,615
NUCENG said:
the effects of curium seem to control the data.

And there's my answer. Thank you.
 
  • #11,616
clancy688 said:
All of these values have the unit of Bq/cm³. http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111102_04-e.pdf" the original.

And this is the original that showed both Aug 9 readings (reported on the 10th) as well as Nov 1. Lower left box is Aug. Why they only tested for Xe-131m and not 133 or 135 is a mystery.
http://www.tepco.co.jp/nu/fukushima-np/images/handouts_111102_01-j.pdf
 
Last edited by a moderator:
  • #11,617
http://spectrum.ieee.org/energy/nuclear/24-hours-at-fukushima" - report by IEEE.

Probably nothing new for most of us who're following this thread regularly but it's still interesting to read.
 
Last edited by a moderator:
  • #11,618
TBS video showing a robot performing debris removal on unit 3's first floor under radiations up to 650 mSv/hour.
 
Last edited by a moderator:
  • #11,619
tsutsuji said:
TBS video showing a robot performing debris removal on unit 3's first floor under radiations up to 650 mSv/hour.


Shows removed by user.
 
Last edited by a moderator:
  • #11,620
  • #11,621
LabratSR said:
Shows removed by user.

New link

The original can be found on Tepco's website in the Japanese language media section : http://www.tepco.co.jp/tepconews/pressroom/110311/index-j.html

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111105_02-e.pdf "Obstacle Removal by Robot and Radiation Dose Measurement after the Removal on the First Floor of Unit 3 Reactor Building at Fukushima Daiichi Nuclear Power Station"
 
Last edited by a moderator:
  • #11,622
Last edited by a moderator:
  • #11,623
I collected some data points given in TEPCOs handouts during the autumn regarding the activity of water to be treated (see attachment). It seems the activity of the accumulated water has decreased by more than half, while its amount has been decreasing as well.

EDIT: The left Y scale should of course be Bq/cm3, not Bq.
 

Attachments

Last edited:
  • #11,624
Rive said:
http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111107_03-e.pdf

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111107_01-e.pdf

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111106_01-e.pdf

Can somebody please tell me why they don't just open the cooling loop and wash it through with the already treated water? With spilling the downcoming to the reactor basement?

Perhaps because the latest TEPCO Status of Countermeasures report indicates the water processing system is running at 53% capacity?
They are pretty much keeping the water level in the plant in check with cooling inflows of about 28 tons/hr.
Adding the SFP flushing water might be a tad much.
It is interesting that the presentation indicates the SFP water will be treated by discrete truck mounted water processing units, not the existing facility.
 
Last edited by a moderator:
  • #11,625
etudiant said:
Perhaps because the latest TEPCO Status of Countermeasures report indicates the water processing system is running at 53% capacity?
They are pretty much keeping the water level in the plant in check with cooling inflows of about 28 tons/hr.

AFAIK that is because the actual goal is to keep a ~ stable water level (a bit lower than the groundwater) instead of trying to dry the basements (which would be impossible).
 
  • #11,626
Rive said:
AFAIK that is because the actual goal is to keep a ~ stable water level (a bit lower than the groundwater) instead of trying to dry the basements (which would be impossible).

Good point.
Of course, while the level for reactors 2-4 is now around the target mark, reactor 1 is still about 4 feet above that, so I doubt they are deliberately slowing down the water processing.
 
  • #11,627
etudiant said:
... reactor 1 is still about 4 feet above that, so I doubt they are deliberately slowing down the water processing.
Check the water level changes in the Plant Status Reports!

If I'm right, U1 is waterproof, the water levels around and inside U1 are moving independently: while for U2, U3 and U4 the water levels are moving in close connection.
 
  • #11,628
Rive said:
Check the water level changes in the Plant Status Reports!

If I'm right, U1 is waterproof, the water levels around and inside U1 are moving independently: while for U2, U3 and U4 the water levels are moving in close connection.


The water level for U1 has always been much different than for 2-4. I'd assumed it was perhaps a siting difference. There was no indication that the OP + 3m water level target excluded U1 afaik.
Given the quake, waterproof seems unlikely. Objectively, the level in U1 has gone down about 60cm if memory serves.
How can you tell inside from outside? is there an indication somewhere in the JAIF report?
 
  • #11,629
what do you think about the sharp Kr-85 rise (in one day) of the famous gas sampling

I stumbled across the fact by looking at

http://enenews.com/just-in-krypton-85-up-over-14000-in-a-day-at-reactor-no-2-kr-85-used-to-detect-plutonium-separations

and do not know what to think of it...
 
  • #11,630
etudiant said:
How can you tell inside from outside? is there an indication somewhere in the JAIF report?
Afaik the 'vertical shaft of the trench' http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111107_06-e.pdf" is the water level in the sub-drain pits around the referenced building (~= local groundwater level).

etudiant said:
The water level for U1 has always been much different than for 2-4. I'd assumed it was perhaps a siting difference.
It's still possible, all what I wrote is a big 'IMHO'.

etudiant said:
Objectively, the level in U1 has gone down about 60cm if memory serves.
As the actual water level goals reached for the other buildings, they are started to work harder on the less urgent one?
 
Last edited by a moderator:
  • #11,633
zapperzero said:
Survey of #4 RB. TEPCO says the blast came from the aircon ducts, on 4th floor

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_111110_01-e.pdf

more photos there

http://www.tepco.co.jp/en/news/110311/index-e.html


I don't think you were saying anything more than "here is the press release", and thankyou for that, but I thought someone else may take your post at face value.

What TEPCO actually said in the document is

" it was possible that the explosion occurred around the
air-conditioning ducts. "

A seemingly obvious and at the same time inconclusive statement.


Aircon ducting is very weak compared to nearly everything else in the RB. There is extensive structural damage to the building and equipment apart from the aircon is severely damaged by flying debris and\or equipment displacement. In several of the images substantial impacts to the remaining ducting are indicative of impacts and\or other forces to the outside of the ducting, deforming it inwards. It isn't beyond the realms of possibility that at least some or even all of the ducting was smashed to pieces from outside forces as opposed to from inside the ducting. The blown out vent mesh would be caused by pressure emanting from within the ducting system, no doubt, but that could in turn have been caused by the ducting being explosively crushed or explosive forces traveling via the ducting, not necesarily explosive force emanating from within it.

I don't believe this latest information gets any closer to a conclusive explanation for a source of hydrogen into RB 4 or whether the explosion emanated from inside the ducting or how\where the hydrogen may have traveled through the building.

However as TEPCO stated, the images do show good evidence that at least one part of the explosive forces that wrecked the building emanated from the fourth floor.
 
Last edited by a moderator:
  • #11,635
Two things I discovered by skimming through the report:

Unit 2 - If I read the section about Unit 2 correctly (and I'm not really sure I did, perhaps NUCENG could look over the sections regarding Units 1-3? There's a certain emphasis on venting valves), then Unit 2 never vented. The workers established a vent path, but a rupture disc never failed, even though the pressure was higher than the pressure needed to break it.
So when Unit 2 finally depressurized, it wasn't done through venting - but through containment failure.

Unit 3 - RCIC didn't fail on March 14th, it failed on March 12th at 11:36 local time, HPCI provided core cooling until the morning of March 14th. Was that fact known before?
 
Last edited:
  • #11,637
clancy688 said:
Two things I discovered by skimming through the report:

Unit 2 - If I read the section about Unit 2 correctly (and I'm not really sure I did, perhaps NUCENG could look over the sections regarding Units 1-3? There's a certain emphasis on venting valves), then Unit 2 never vented. The workers established a vent path, but a rupture disc never failed, even though the pressure was higher than the pressure needed to break it.
So when Unit 2 finally depressurized, it wasn't done through venting - but through containment failure.

Unit 3 - RCIC didn't fail on March 14th, it failed on March 12th at 11:36 local time, HPCI provided core cooling until the morning of March 14th. Was that fact known before?

It does not seem to me like there is much in the way of new information in this report, but it is presented in a way that makes it easier to spot such details. We already knew that they had numerous problems trying to vent reactor 2, and although I am not sure we spent much time talking about it. The fact that venting never happened does not strike me as new, although prior to this latest report I am not sure it was ever specifically stated that rupture disc never failed.

Checking the info from that report with a couple of other sources such as NISA analysis of events, my brief summary of venting details for the three reactors is as follows:

Reactor 1
RPV fell to PCV pressure levels without any mention of SRV valves having been deliberately opened
PCV pressure fell somewhat, and radiation levels at plant increased, before there was any venting.
Early venting attempts were only partially successful or not successful at all for hours on the 12th.
Venting was eventually confirmed, backed up by visual evidence of venting via stack.

Reactor 2
Numerous problems when trying to get various vent paths opened.
SRV's opened on more than one occasion.
PCV pressure didn't rise significantly when RPV pressure first fell, suggesting PCV leak.
RPV pressure increased several times after initial SRV opening, requiring further SRV opening activity to be performed.
PCV pressure then went higher, but the indicated drywell pressures went much higher than the suppression chamber ones.
Venting still didn't work.
Tried to vent directly from drywell to get round the issue of lower s/c pressure compared to d/w pressure, but there was still no indication of success.
Sound near suppression chamber, pressure indication for s/c went to 0, drywell pressure fell over the next few hours.

Reactor 3
RPV pressure fell when HPCI started.
RPV pressure increased when HPCI failed.
Attempts to vent not successful.
PCV containment leaking may have occurred.
Venting succeeded, with visual confirmation of venting via stack. SRV opened at about the same time and RPV pressure fell as expected.
Problems keeping vent path open at certain times in the subsequent days, which sometimes affected ability to continuously inject enough water.
 
  • #11,638
TEPCO have released a large number of previous unpublished videos, taken over many months.

http://www.tepco.co.jp/en/news/110311/111111-e.html
 
Last edited by a moderator:
  • #11,639
SteveElbows said:
TEPCO have released a large number of previous unpublished videos, taken over many months.

http://www.tepco.co.jp/en/news/110311/111111-e.html

It says there
<quote>These motion pictures are available until the end of December. </quote>
so make copies
 
Last edited by a moderator:
  • #11,640
This was the first "extended SBO + all EDGs off" scenario, and it resulted in a total, 100% SNAFU: not a single reactor unit was saved.

It's actually worse than that: out of three active reactor units affected, FOUR blew up (counting 2nd unit's infamous "load bang in the torus area"): they managed to blow up even the unit with reactor switched off, opened and unloaded. That's quite an achievement.

Tell me how I can trust nuclear industry after this. Am I to believe French or US nuclear stations are better prepared, when more natural and conservative conclusion is 'French and US nuclear stations just didn't have their "extended SBO + all EDGs off" scenario. Yet. Just wait'?
 
  • #11,641
nikkkom said:
It's actually worse than that: out of three active reactor units affected, FOUR blew up

Great line, I really had to laugh out loud. Both hilarious and depressing.

Tell me how I can trust nuclear industry after this. Am I to believe French or US nuclear stations are better prepared, when more natural and conservative conclusion is 'French and US nuclear stations just didn't have their "extended SBO + all EDGs off" scenario. Yet. Just wait'?

I agree, trust is gone, for me, too. I was totally pro-nuke before Fukushima, but now I'm against it.
But overall I'd say that damn tsunami probably chose the one plant out of all those 500 stations in service worldwide which was actually the most vulnerable against such an attack. Pretty bad luck I'd say. And keep in mind that the whole station was from the same generation as Chernobyl and even TMI.
(By the way, we had three major accidents in civil NPPs and all of them happened in Units designed and built in the late sixties...)
 
  • #11,642
clancy688 said:
(By the way, we had three major accidents in civil NPPs and all of them happened in Units designed and built in the late sixties...)

I blame the pot. On a more serious note, I think it has been definitively proven unwise to operate NPPs that are past their design life.

Oh, if only decommissioning one were not such an involved and costly affair.
 
  • #11,643
Is this a technical forum - or a political one?

With enviornmental whackos preventing construction of coal fired base load plants and opposing ALL new nukes what PRACTICAL alternative is there? Hard to shut down an operating plant when there is nothing to replace it!

These kooks would have us all freeze to death in the dark.

If I choose to be anti-nuke I want it based on sound science, NOT political considerations or activist driven pseudo science.

I come here to study and learn science.
 
  • #11,645
http://www3.nhk.or.jp/news/genpatsu-fukushima/20111107/2100_hoanin.html The NISA declared that Tepco's report on Xenon was valid.

http://www3.nhk.or.jp/news/genpatsu-fukushima/20111110/0500_kanshi.html Tepco said it would implement a system to measure Xenon continuously, for the purpose of being able to quickly assess criticality. Concerning temperature measurements, Tepco said that there is a 20°C uncertainty, so that in order to be sure to achieve 100°C as requested by the "cold shutdown" requirement, the thermometer values have to be below 80°C.

http://www3.nhk.or.jp/news/genpatsu-fukushima/20111109/1400_kouteihyo-shiji.html and http://www3.nhk.or.jp/news/genpatsu-fukushima/20111109/1650_30nen.html The ministers of Industry (Edano) and Nuclear accident (Hosono) have asked Tepco to prepare a schedule where spent fuel pool fuel removal is started within 2 years after completion of step 2. This is one year earlier than recommended in the report from the middle and long term commission that was completed on 9 November. Concerning molten fuel removal, the start is within 10 years.

http://www3.nhk.or.jp/news/genpatsu-fukushima/20111112/0615_tsuruga.html The NISA is asking Japco to provide the operation data of the isolation condenser of Tsuruga unit 1 over the past 10 years because it is similar to the one of Fukushima Daiichi unit 1, and it might shed light on what went wrong at Fukushima Daiichi.
 
Last edited by a moderator:
  • #11,646
clancy688 said:
I agree, trust is gone, for me, too. I was totally pro-nuke before Fukushima, but now I'm against it.
But overall I'd say that damn tsunami probably chose the one plant out of all those 500 stations in service worldwide which was actually the most vulnerable against such an attack. Pretty bad luck I'd say.

How did you figure that out?
Do a mental exercise: imagine that all EDGs on all NPPs on the planet have vanished into thin air; then cut all power - put all NPPs into extended SBO.
Can you honestly say that F1 would be the only station where in this mental experiment events would take the worst turn? All other ones would be better off? That's statistically unlikely.

And keep in mind that the whole station was from the same generation as Chernobyl and even TMI.

We were told that they are upgraded with new safety systems and thus are safe. We ended up with station personnel not knowing how to turn on ICs and/or vent containment without electricity.
 
  • #11,647
nikkkom said:
put all NPPs into extended SBO.
Can you honestly say that F1 would be the only station where in this mental experiment events would take the worst turn?

Um, nope. I rather meant that the SBO only happened because the tsunami "chose" the single one plant which would actually lose everything if hit.
True, other plants will probably live through the same experience if confronted with a multiple-day SBO. But the actual event (earthquake + tsunami) may not be enough to trigger such a SBO at other stations.
A NPP will suffer meltdowns if confronted with a long and total SBO. And a plane will crash if all engines fail and can't be restarted. That's why you engineer those things the way that this shouldn't happen. But at Fukushima, nobody apparently thought of the obvious, a giant tsunami inundating the whole plant, and that triggered the SBO.
In my opinion, the problem is not the SBO. It are the events which could lead to SBOs. Or high-pressure meltdowns. Or whatever else. The events which no engineer thought of when constructing the plant. And those events exist, as Fukushima proved.

We were told that they are upgraded with new safety systems and thus are safe. We ended up with station personnel not knowing how to turn on ICs and/or vent containment without electricity.

Is it even possible to turn ICs on/off and/or vent the containment without electricity? I honestly don't know.
 
  • #11,648
clancy688 said:
Two things I discovered by skimming through the report:

Unit 2 - If I read the section about Unit 2 correctly (and I'm not really sure I did, perhaps NUCENG could look over the sections regarding Units 1-3? There's a certain emphasis on venting valves), then Unit 2 never vented. The workers established a vent path, but a rupture disc never failed, even though the pressure was higher than the pressure needed to break it.
So when Unit 2 finally depressurized, it wasn't done through venting - but through containment failure.

Unit 3 - RCIC didn't fail on March 14th, it failed on March 12th at 11:36 local time, HPCI provided core cooling until the morning of March 14th. Was that fact known before?

I am not sure I can add much to what you have read. I have one criticism as this report is a narrative and does not provide references on how each statement was developed. As a result I think we need to review the vast amount of claims, statements, descriptions and timelines to find support or conflict. OTOH, this is exactly the kind of event summary that can make that a manageable exercise.

The narratives of units 1 to 4 are all plausible as far as I can see. I was sceptical about the Unit 3 source for the hydrogen explosion in unit 4, but the recent photos of damage on the 4th floor are persuasive, if not conclusive. I thought that the reverse flow through the unit 4 SBGT filters was problematic. But this report explains that unit 3 was able finally to vent at a fairly high containment pressure. It clarifies that the SBGT system dampers fail open. It confirms there are no backdraft dampers to prevent flow to the adjacent unit.

From the descriptions I note a new issue that may affect other multiple unit sites. The military term is fratricide and refers to casualties to friendly forces close to a an intended target. Unit 1 explosion damaged response equipment at unit 2. Unit 3 explosion damaged additional response equipment for other units. The issue here is the physical separation of units or location of emergency hookups to shield the equipment and workers from failures in adjacent units.

On Unit 2 There are two things to point out. First RCIC probably failed due to inability to cool or rediuce pressure in containment. RCIC exhausts to the suppression pool and the combination of low steam pressure and high exhaust pressure was the probable cause of RCIC failure. I see nothingin the report that indicates unit 2 containment venting was successful. Containment failure of the torus is still a likely explanation for the "loud noise."

I had seen the reports that unit 3 had HPCI running when the preferred system should have been RCIC which failed. This is another example of an issue that needs careful investigation. The number of work-arounds and alternative methods tried by operators to vent containments, operate SRVs, provide alternate power to instruments, and to reenergize other systems was very impressive. But it is probable that some of these methods were subject to delays to figure out how to do them. In my experience, some of these methods are proceduralized and exercised at US plants.

Hope this helps the discussion.
 
Last edited:
  • #11,649
clancy688 said:
Um, nope. I rather meant that the SBO only happened because the tsunami "chose" the single one plant which would actually lose everything if hit.
True, other plants will probably live through the same experience if confronted with a multiple-day SBO. But the actual event (earthquake + tsunami) may not be enough to trigger such a SBO at other stations.
A NPP will suffer meltdowns if confronted with a long and total SBO. And a plane will crash if all engines fail and can't be restarted. That's why you engineer those things the way that this shouldn't happen. But at Fukushima, nobody apparently thought of the obvious, a giant tsunami inundating the whole plant, and that triggered the SBO.
In my opinion, the problem is not the SBO. It are the events which could lead to SBOs. Or high-pressure meltdowns. Or whatever else. The events which no engineer thought of when constructing the plant. And those events exist, as Fukushima proved.



Is it even possible to turn ICs on/off and/or vent the containment without electricity? I honestly don't know.


The report explains that the containment vent valves had manual operation capability and that operators eventially provided additional pneumatic pressure (compressor and air bottles) and alternative power from batteries to operate the system. In addition to remote operation from the control room theat means there were multiple ways to operate the valves, including manual and alternate power.
 
  • #11,650
nikkkom said:
How did you figure that out?
Do a mental exercise: imagine that all EDGs on all NPPs on the planet have vanished into thin air; then cut all power - put all NPPs into extended SBO.
Can you honestly say that F1 would be the only station where in this mental experiment events would take the worst turn? All other ones would be better off? That's statistically unlikely.



We were told that they are upgraded with new safety systems and thus are safe. We ended up with station personnel not knowing how to turn on ICs and/or vent containment without electricity.

nikkom, a mental exercise probably doesn't belong on this thread. But while you're at it why not throw in a loss of gravity accident? :rolleyes:
 

Similar threads

Replies
12
Views
49K
Replies
2K
Views
447K
Replies
5
Views
6K
Replies
2
Views
2K
Replies
763
Views
272K
Replies
38
Views
16K
Replies
4
Views
11K
Back
Top