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Japan Earthquake and Tsunami

Morwax

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Again the documents that I have been reading on these plants have stated a 6in SS conefinement vessel, with respects to the cladding with low carbon steel. I have been looking for reference to the plants but have not found any. If you have found info on their designs then please link it.

That stuff is classified.
 

Puck it

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That stuff is classified.

Not really. I will dig further and see if this design is clad. I think the reactor at this site was manufactured by Westinghouse. I should be able to dig it up and find out. Stainless steel is able to handle the pressure with a strength of ultimately 860MPa. The cooling water in BWR is maintained at about 7.6MPa. The PWR reactor is higher at 16MPa. It may be cladded now due to cost of the stainless and the experience of 40 years.

BTW, if you had a problem with my information. Do not act like dmz. I would have been happy to discuss your information, but you went about it with an attack and that pisses me off more then you think.

Thanks to C-10 and Wa.
 

deadheadskier

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FWIW

Nuke expert on NPR today claimed the internal contianment vessels are stainless steel, then surrounded by 6 inch thick concrete.

Also said that Japan recycles spent rods
 

Cannonball

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This is valuable stuff. I have stopped listening to all other media outlets and am now getting my news about the disaster in Japan only from the miscellaneous discussion section of a northeast US skiing forum. DMC makes for a great new transcriber, drawing on sources as far reaching as Youtube. And Puck it is the go to guy for in-depth “I work in a similar field and know some people who do this stuff” analysis. Plus it’s highly informative to get differing analysis from other specialists who also know how to use Google.
 

deadheadskier

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This is valuable stuff. I have stopped listening to all other media outlets and am now getting my news about the disaster in Japan only from the miscellaneous discussion section of a northeast US skiing forum. DMC makes for a great new transcriber, drawing on sources as far reaching as Youtube. And Puck it is the go to guy for in-depth “I work in a similar field and know some people who do this stuff” analysis. Plus it’s highly informative to get differing analysis from other specialists who also know how to use Google.

Come on man. Don't I get any credit for reporting what I hear on NPR? :lol:
 

Puck it

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FWIW

Nuke expert on NPR today claimed the internal contianment vessels are stainless steel, then surrounded by 6 inch thick concrete.

Also said that Japan recycles spent rods

The concrete is what I am referring to as secondary confinement. The question morwax is bringing up is the primary confinement aka vessel all stainless or stainless lined clad by a low carbon steel. I am researching that. I have heard what you have that the vessel was all stainless and 6 inches thick. I am mining now for the manufacturer info. Stay tuned.
 

Cannonball

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Wanna meet up. I was supposed to go with some guys from work but they are bagging I think.

Sure. I have a buddy coming up who's good rider but it'll be his first time out this year (tough times). That could impact my usual plan of attack and could make for a slower day. Still, should be good spring conditions and good fun. I'll PM my #.
 

Puck it

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Sorry, it did not paste well from the pdf file that I found.

The vessel is listed below as ASTM A533 bCl 1 alloy, which is Tempered Manganese-Molybdenum-Nickel. This a non-reactive steel alloy desgin for pressure vessels. This could where the reports may have assume it was stainless from what I was reading I should have dug farther. The wall thickness is alittle over 6 inches. The cladding is 5mm and the wall thickness is 160mm. I need to dig more to find what material the cladding is and what material the wall is. Containment vessel design pressure is about 62psi. Well within any steel or stainless steel strength. The other question is this alloy handle embrittlement better. Stayed tuned.


Full specs on Mark 1 General Electric BWR/3 design


Fuel and Cladding
Fuel UO2 pelletCladding Zr-2 Enrichment Initial: 2.1 %
Reload: 3.4 %
Pellet Height 10.3 mmPellet Diameter 10.4 mmClad Thickness 0.86 mmPin Height 3945 mmPin Outside Diameter 12.3 mmMaximum Clad Temperature 310 deg CMaximum Centerline Temperature 1690 deg C

Fuel Assemblies
Assembly Model Initial Core: 7x7
Reloads: 8x8 high burnup
Number of Rods per Assembly 60 Fuel Rod Pitch 1.6 cmTotal Number of Assemblies 400 Fuel Assembly Pitch 15.2 cmGeometry 8x8

Core Configuration
Active Core Height 3.66 mActive Core Diameter 3.44 mFuel Inventory 68 tHMAverage Core Power Density 40.6 kWt/literAverage Assembly Discharge Burnup 39500 MWd/tUPeak Assemby Discharge Burnup 50000 MWd/tUNumber of Cycles to Full Burnup 4 Axial Blankets yes Axially Zoned Fuel yes Axially Zoned Burnable Poisons yes Average Linear Fuel Rating 15.10 kW/mPeak Linear Fuel Rating 44.00 kW/m

Control System
Control Rod Material B4C/Hf Control Rod Drive Type hydraulic Number of Coarse Control Rods 97 total Number of Rods Containing Burnable Poison 9/11 Burnable Poison Material Gd2O3 Other Control Systems burnable poison/recirculating

Primary Coolant
Coolant Material H2O Weight in Primary Circuit 148 tPressure 70.7 kg/sq cmCore Inlet Temperature 183 deg CCore Outlet Temperature 285 deg CNumber of Primary Pumps 2 Total Mass Flow 21800 t/h

Coolant Systems
Number of Loops 2 Water Chemistry

Turbines
Number of Turbines 1 Turbine Speed 1500 rev/minTurbine Undefined subroutine &main::newrx_data_finish called at /opt/netscape/htdocs/insp/cgi-bin/rperl/sql_interface line 48. Rating 460 MWeStop Valve Pressure 66.8 kg/sq cmStop Valve Temperature 282 deg C

Vessel and Containment
Vessel Material ASTM A 533 B Cl 1 Vessel Shape cylinder Height 19.7 mInner Diameter 4.8 mWall Thickness 160 mmClad Thickness 5 mmContainment Type pressure suppression Containment Design Pressure 4.35 kg/sq cm

Reactor Operations
Cycle Length 13 monthsNormal Planned Outage Length 90 daysFuel Loading 10 tHM/yFraction of Core Reloaded Each Cycle 25 %Operational Strategy Low Leakage Fuel Management


Spent Fuel Management Number of Operating Cycles Completed 15 Pool Capacity Increase Strategy 75.0 Total Increase in Pool Capacity Reracking %Other On-Site Storage Common storage pool Supplier of Additional Storage Toshiba
 
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Puck it

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Sure. I have a buddy coming up who's good rider but it'll be his first time out this year (tough times). That could impact my usual plan of attack and could make for a slower day. Still, should be good spring conditions and good fun. I'll PM my #.

I park over at Zoomer with my silver FJ cruiser. PM your number.
 

dmc

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DMC makes for a great new transcriber, drawing on sources as far reaching as Youtube.

I didn't major in physics in college.. I majored in journalism..

Although i enjoy the effects of physics on my snowboarding... :)
 
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