Japan Earthquake: Nuclear Plants at Fukushima Daiichi

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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.
  • #12,121
http://www3.nhk.or.jp/news/genpatsu-fukushima/20120110/index.html 10 litres of partly decontaminated water were found at around 10 AM on January 10 on the concrete below a tank. The leaked was stopped by tightening a junction bolt. Tepco says the water did not leak to outside the plant premises.

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_120110_03-e.pdf " Water leakage from the concentrated water tank of the water desalinations (reverse osmosis membrane)"

matthewdb said:
The turbine is not normally approached under power due to gamma from N-17.

What does N-17 stand for ?
 
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  • #12,122
tsutsuji said:
http://www3.nhk.or.jp/news/genpatsu-fukushima/20120110/index.html 10 litres of partly decontaminated water were found at around 10 AM on January 10 on the concrete below a tank. The leaked was stopped by tightening a junction bolt. Tepco says the water did not leak to outside the plant premises.

http://www.tepco.co.jp/en/nu/fukushima-np/images/handouts_120110_03-e.pdf " Water leakage from the concentrated water tank of the water desalinations (reverse osmosis membrane)"



What does N-17 stand for ?

Nitrogen.
 
  • #12,123
zapperzero said:
Nitrogen.

How is it generated ?
 
  • #12,124
It's N-16, not N-17, and it's produced by neutron irradiation of the oxygen O-16 from the steam in the reactor with (n,p) reaction (a neutron knocks out a proton from the oxygen). It has a very short half-life of about 7 seconds, but that's enough to make all pipelines containing steam difficult to approach during the operation of a BWR plant.
 
  • #12,125
I found the following via google:

In the EPR (a PWR) "the main radioactive sources responsible for external radiation near the primary circuit are nitrogen-16 (gamma emitter), nitrogen-17 (neutron emitter) and the core (gamma rays and neutrons)" http://www.epr-reactor.co.uk/ssmod/...pter 12.3 - Radiation protection measures.pdf

"The only case [of neutron decay] which is of some interest in nuclear technology is the neutron decay of nitrogen 17, formed by fast neutron irridiation of oxygen 17" http://books.google.com/books?id=E7Em_V7Zq9sC&pg=PA162

http://icanps.go.jp/111226Siryo2.pdf (Attachments for the cabinet investigation committee interim report, part II) A layout plan of Fukushima Daiichi unit 1's reactor building first floor is available on page 23, and that of the turbine building first floor is available on page 25. The north side (on the top of page 23 or on left of page 25) and south side (on the bottom of page 23 or on right of page 25) airlocks are clearly visible between turbine and reactor buildings. You may also want to have a look at the reactor building's fourth floor on page 21, where IC (A), IC (B) and the exhaust vents (pig nose) are represented.
 
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  • #12,126
Pakman said:
Ok, I just guessed. So it needed to change "airlock" to "tightly closing door" in what I've written above. But then the talking was about the reactor building.

Not necessarily a tightly closing door - they are just high quality ordinary security doors. Plants rely on positive airflow from the ventilation systems. Airflow is arraigned to flow first to areas people will occupy and then is ventilated out from the areas of highest contamination.

Pakman said:
Through the vent stack, I believe? What happens with level of radiation inside the building when ventilation stops?

All reactor building ventilation goes through the stack. As does the condenser vent and the turbine gland exhauster. The flow rate from the turbine building is VERY high to keep the building temperature in check so it doesn't go up the stack. We're talking flows on the order of 2 million m^3/h in a large plant.
 
  • #12,127
tsutsuji said:
I found the following via google:

In the EPR (a PWR) "the main radioactive sources responsible for external radiation near the primary circuit are nitrogen-16 (gamma emitter), nitrogen-17 (neutron emitter) and the core (gamma rays and neutrons)" http://www.epr-reactor.co.uk/ssmod/...pter 12.3 - Radiation protection measures.pdf

I was incorrect at stating it is N-17, thanks rmattila.

The N-16 is the majority of the immediate dose since the high energy gamma penetrates the piping. N-17 is a concern over time because it slowly activates the metal of the piping and turbines.

The N-16 is extracted at the condenser. After that the feed piping is quite low in activity so you won't see much shielding on the feed piping. The exhaust of the condenser is retained for 10 minutes by sending it through a long, folded up pipeline.

In a PWR the amount of N-16 in the steam is monitored as an indicator of the leak rate of the steam generators.
 
  • #12,128
tsutsuji said:
http://icanps.go.jp/111226Siryo2.pdf (Attachments for the cabinet investigation committee interim report, part II) A layout plan of Fukushima Daiichi unit 1's reactor building first floor is available on page 23, and that of the turbine building first floor is available on page 25. The north side (on the top of page 23 or on left of page 25) and south side (on the bottom of page 23 or on right of page 25) airlocks are clearly visible between turbine and reactor buildings. You may also want to have a look at the reactor building's fourth floor on page 21, where IC (A), IC (B) and the exhaust vents (pig nose) are represented.

I think we have multiple uses of the word "airlock" meaning quite different things. At the entrance to the reactor building there are double doors forming an airlock that prevents disruption of the normal airflow pattern to prevent undesired contamination movement. These are your typical industrial doors with weather-striping type gaskets. They are only able to withstand very low pressures generated by ventilation systems.

There are similar doors at the entrance to the control room to prevent entry of contamination in an accident.

To enter the primary containment there are bolted hatches with gaskets able to withstand rated containment pressure. Whenever I've heard the term "airlock" they are referring to the primary containment entry. In the pdf these are visible on page 27 between the reactor building and the primary containment.
 
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  • #12,129
Talking of ventilation:

http://www.tepco.co.jp/en/press/corp-com/release/12011005-e.html

Operation of ventilation and air-conditioning system at reactor building
of unit 5 and 6 has been suspended since March 11, 2011. We have been
carrying restoration works and checks to repair the system to prevent the
equipment from degradation aiming for keeping the stable cold shutdown and
improve the high-humidity environment in the building. Now the system is
ready to operate and so we will start the operation of the system at 13:30
pm on January 11, 2012.
The operation of the system leads air inside of reactor building to be
exhausted through main exhaust stack of unit 5 and 6. However, we will
monitor the exhausted air by radiation monitor (exhaust monitor) that is
the same as the way we monitor them before March 11, 2011, and also we
will exhaust the air through newly installed high performance particle
filter placed at both intake and exhaust sides at air-condition equipment
in reactor building to reduce the level of radioactive.
 
  • #12,130
""The N-16 is extracted at the condenser. ""

is there not a quite lengthy maze of pipe in main steam line between reactor and turbine, for purpose of delaying steam's arrival until n16 has mostly decayed away?

and that's why there's so much volume in some of those basements, they are huge rooms surrounding that pipe?

tsujitsu -
"How is it generated ? "
n16's halflife is in seconds as rmatlla said. so it's quite active because half of it decays every 7 seconds.
in pwr it's the reason we can't go around the primary loops at power. it has an energetic gamma ray accompanying its beta decay..


in case you've not tinkered with chart of the nuclides:
http://www.nndc.bnl.gov/chart/chartNuc.jsp
type n16 into "nucleus " box,
click "go" button then "zoom 1" above

have fun!
 
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  • #12,131
jim hardy said:
""The N-16 is extracted at the condenser. ""

is there not a quite lengthy maze of pipe in main steam line between reactor and turbine, for purpose of delaying steam's arrival until n16 has mostly decayed away?

No. The pipe routing in a BWR and a PWR are quite similar. The pipes are big and expensive and the owner of the plant doesn't want to buy more than they have to. They are around 3/4 m in diameter and there are 4 in parallel. 70 seconds of pipe would be an incredible maze.

jim hardy said:
and that's why there's so much volume in some of those basements, they are huge rooms surrounding that pipe?

The biggest item on the lowest level is the condenser. In a 1GW plant the condenser is around 12m tall, 20m wide and 40m long and there are three of them. The condensate pumps have to be in the basement to provide suction head (actually well below basement grade in a pit). Water in the condenser is at saturation temperature and the motive force is gravity; if a pump were to try and lift condensate it would just flash to steam.

If open feed heaters are used, the feed pumps must be located at the lowest level to provide suction head to them too.
 
  • #12,132
Steam velocity in the steam lines is typically some 50 m/s, so the steam does not spend a long time traveling to the turbine. There is some delay in the top of the reactor vessel, but all the steam lines up until the condenser ejectors are pretty active during operation. Some 10 mSv/hr is normal in the vicinity of the steam line outer isolation valves.
 
  • #12,133
jim hardy said:
is there not a quite lengthy maze of pipe in main steam line between reactor and turbine, for purpose of delaying steam's arrival until n16 has mostly decayed away?

matthewdb said:
No. The pipe routing in a BWR and a PWR are quite similar. The pipes are big and expensive and the owner of the plant doesn't want to buy more than they have to. They are around 3/4 m in diameter and there are 4 in parallel. 70 seconds of pipe would be an incredible maze.

Yeah, I think some PWRs have a run of 'delay pipe' in the letdown line for N-16 decay, maybe that's what jim hardy is thinking of. For 70 seconds at 132 gpm you'd need about 20 cubic feet of pipe.
 
  • #12,134
For PWR it's vital, yeah.
 
  • #12,135
Well. The conditions you mentioned above can tell you that more likely there's no significant threat to human's life in the reactor building as long as fuel is covered. You just need to know how long.

Of course, then you tell me that is not enough to enter the building, since there's no 100% gurantee. I skip this conversation and answered right to the last in terms, that who does not want to do their job, will always find an excuse.
 
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  • #12,136
bravado and big machinery is a bad combination.

if one wants to know the position of a valve he can lift leads in control room and read position switches with an ohm-meter
or find whether there's flow downstream of it
without endangering his co-workers (they'd have to go in and drag him out)

i won't criticize anyone's actions in a disaster zone without first-hand knowledge of the circumstances.

the trouble with harsh words is one so often has to eat them.
 
  • #12,137
Doubts and hesitancy is what really can not be combined with large machines. Or you're ready for taking action in the same plant conditions and you say this or you're polite.

Jim, you said you're an old instrument guy, so you're not an operator? Real operator, i mean, heat guy? May be because of this all your doubts are?

You think just like an instrument guy. Of course it's possible to check switches with ohm-meter. What if the valve position is not what you want? How will you operate it? Using ohm-meter's accumulator?
 
  • #12,138
Morbius said:
It takes a mixture of hydrogen and oxygen to be explosive. One or the other but not both doesn't give you an explosive mixture.

This reminds me of all the concern during the Three Mile Island accident concerning the "hydrogen bubble". The concern is that it was going to explode and breach the system piping.

Greg

Page 99 of the he Presidential Commission report says there was a hydrogen explosion inside the containment building.
http://www.threemileisland.org/virtual_museum/pdfs/188.pdf

Has anyone figured out what ignited the hydrogen/oxygen mix in the Fukushima explosion? I read that the first explosion happened right after they had hooked up power to the building.
 
  • #12,139
Jim, you said you're an old instrument guy, so you're not an operator? Real operator, i mean, heat guy? May be because of this all your doubts are?

You think just like an instrument guy.

guilty as charged, Pakman. I am an old instrument guy.

i have highest regard for operators. they have a different psychology, ability to stand back and assess whole situation.
my makeup causes me to focus on small details.( google aspergers)
i would not make a good operator.

old men err by thinking too much before they'll act.
young men err by thinking too little before they act.

that's why one wants a mix of fresh thinking and experience.

in emergency, somebody with suitable talents chooses between the courses of action recommended to him.

if the shift supervisor asked me to go in, knowing the conditions were i might not come back out, i would go. I'm 65 and my kids are grown.
but i wouldn't place him in situation of having to answer "why'd you let him do that?"
and neither should a younger man

old jim
 
  • #12,140
I was an NPP operator. I can't imagine to myself the situation, when my shift supervisor being unaware about reactor cooling status wouldn't send me immediately anywhere he is thinking it is necessary, to check what he wants to be checked. He will never be guessing if the reactor is cooled or not. In case of high radiation, if we refused to do the task, he will go there personally by himself
 
  • #12,141
r-j said:
Page 99 of the he Presidential Commission report says there was a hydrogen explosion inside the containment building.
http://www.threemileisland.org/virtual_museum/pdfs/188.pdf

Has anyone figured out what ignited the hydrogen/oxygen mix in the Fukushima explosion? I read that the first explosion happened right after they had hooked up power to the building.

i think what cause the water to be dissociated the beryllium tube will be the factor for the ignition because when burning it is creating flashes
 
  • #12,142
if we refused to do the task, he will go there personally by himself
If you encountered drastically different radiation than he expected, surely you'd tell him? That sounds like an important indication as to state of things.

Morning of TMI an electrician brought an old fashioned bridge to the control room and read the millivolts comiing from incore thermocouples.
He observed they were well above 650 degrees, i think approaching a thousand (F).
(some ill advised person had programmed plant computer to display question marks when readings got that high, so operators were confused by disparate indications.)
He had Navy experience and advised control room operators "You need more water in there..."

i don't know why that key information was dismissed. Perhaps it didn't get to SS.


if we refused to do the task, he will go there personally by himself

just like you, i can't imagine that becoming necessary.
 
  • #12,143
r-j said:
Has anyone figured out what ignited the hydrogen/oxygen mix in the Fukushima explosion? I read that the first explosion happened right after they had hooked up power to the building.

Hydrogen is phenomenally easy to ignite. With most fuels it is effective to control ignition sources to prevent explosions. With hydrogen it is irrelevant. You must prevent explosive mixtures from forming because minute static discharges from airflow can ignite it.
 
  • #12,144
jim hardy said:
If you encountered drastically different radiation than he expected, surely you'd tell him? That sounds like an important indication as to state of things.

Morning of TMI an electrician brought an old fashioned bridge to the control room and read the millivolts comiing from incore thermocouples.
He observed they were well above 650 degrees, i think approaching a thousand (F).
(some ill advised person had programmed plant computer to display question marks when readings got that high, so operators were confused by disparate indications.)
He had Navy experience and advised control room operators "You need more water in there..."

I didn't think they had malfunctioning sensors at TMI, just a failure to understand their meaning. They didn't consult a steam table to realize that the pressure and temperature they had were for steam not sub-cooled water. Because of this all PWM plants in the US now have a subcooling calculator with a readout in the control room. That and not recognizing a rising temperature in containment and sump pump operation to indicate a LOCA.

They did get a surprise when they asked for a primary water sample. The chem tech reported brown primary water with incredible activity. At that point they realized they had a fuel melt.

Perhaps you're confusing this with the Browns Ferry U1 control room fire? They measured the RPV water level and pressure and the containment temperature and pressure using a multimeter in one of the electrical rooms. They then shut the plant down by operating the RCIC and containment cooling locally and operating the blow-down valves via a makeshift switch.
 
  • #12,145
senior nuke QA Engineer here...how are things going at the plant?
 
  • #12,146
what do you think about letting the cavity water boil for 48 hours, while the reginative heat exchangers are being repaired...the fuel pool was also boiling?Am I over reacting?
 
  • #12,147
""I didn't think they had malfunctioning sensors at TMI, just a failure to understand their meaning. They didn't consult a steam table to realize that the pressure and temperature they had were for steam not sub-cooled water. Because of this all PWM plants in the US now have a subcooling calculator with a readout in the control room. ""



their plant computer wasn't malfunctioning, it was simply programmed to display question marks instead of readings that were higher than whoever programmed it thought possible.
That's why the fellow read them with a bridge type millivolt meter.
displaying question marks for beyond-expected thermocouple readings became an industry issue , we had to answer numerous inquiries and provide assurance that ours wasn't programmed that way.


indeed, i too read report they had no steam table in the control room.
It seemed to take forever to get an electronic subcooling meter bought and installed. Meantime i pulled the wide range pressure meter, which was an analog instrument with a needle and printed scale, and wrote alongside each major scale division the corresponding saturation temperature, put it back in panel...
works great because almost adjacent to that meter is the temperature indicator.

but I'm way off topic.

over and out.
 
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  • #12,148
djm51x said:
what do you think about letting the cavity water boil for 48 hours, while the reginative heat exchangers are being repaired...the fuel pool was also boiling?Am I over reacting?

??
Can you please give me some links or something about this?
 
  • #12,149
And what is with unit 2 temperature: http://www.tepco.co.jp/nu/fukushima-np/f1/images/12011612_temp_data_2u-j.pdf ?
 
  • #12,150
Corium runs down the control rod drive
 

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