Spent Fuel and Spent Fuel Storage Facilities at Fukushima Daiichi
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1 Spent Fuel and Spent Fuel Storage Facilities at Fukushima Daiichi The National Academies Lessons Learned from the Fukushima Nuclear Accident for Improving Safety and Security of U.S. Nuclear Plants: Phase 2 2 Meeting #3 Washington, DC January 29 th, 2015 Kenji Tateiwa Manager, Nuclear Power Programs Tokyo Electric Power Company, Washington Office tateiwa.kenji@tepco.co.jp
2 2 Current Status of Fukushima Daiichi (1F) View 1 Unit 1 Unit 2 Unit 3 View 2 Live Camera View (as of 1/29/2015) Unit 1 Unit 3 Unit 2 Unit 4
3 Overview of the 10-Unit Simultaneous Accidents 3 Date /11 3/12 1 Fukushima Daiichi (1F) Fukushima Daini (2F) 2 3 3/11 15:27 1 st Tsunami, 15:35 2 nd Tsunami 3/11 15:22~ Tsunamis Station Blackout Water Injection: NO Heat Removal: NO 3/12 15:36 Unit 1 Explosion 3/12 8:13 D/G-6B Water Injection: YES Heat Removal: NO 3/12 12:15 4 3/13 3/14 3/15 3/14 11:01 Unit 3 Explosion 3/15 6:00-6:10 Unit 4 Explosion Loss of Ultimate Heat Sink 3/14 1:24 RHR 3/14 17:00 3/14 7:13 RHR 3/14 18:00 3/14 15:42 RHR 3/15 7:15 3/ /19 5:00 RHR 3/19 22:14 RHR 3/20 3/20 15:46 P/C-2C 3/20 15:46 P/C-2C 3/22 10:36 P/C-4D 3/22 10:35 P/C-4D 3/20 14:30 3/20 14:30 Water Injection: YES Heat Removal: YES Cold Shutdown
4 Spent Fuel Storage Facilities: Overview Temporary Dry Cask Storage Facility Common Pool U6 U5 U1 U2 U3 U4 Dry Cask Storage Bldg. Fukushima Daiichi NPS Unit Common Pool Dry Cask Storage Temp. Dry Cask Storage Spent Fuels - As of 3/11/ , , New Fuels Decay Heat (MW) /22/2014 Total # of Fuels ,884 6, ,
5 Unit 1 Spent Fuel Pool: Water Injection 5 Date (2011) Injection Volume (ton) Source Injection Method Water Injection into SFP with Concrete Pumper 3/31 5/20 5/22 5/28 5/29 6/5 7/5 8/5 8/10 8/ Fresh Water Concrete Pumper Fuel Pool Cooling (FPC) System Closed Cycle Cooling Injected only fresh water (no seawater)
6 Unit 1 SFP: Closed-Cycle Cooling 6 Skimmer Surge Tank Air Fin Cooler Secondary Loop FPC Hx Spent Fuel Pool FPC Pump Primary Loop Water Injection Stable closed-cycle cooling from 8/10/2011
7 Unit 1 SFP: Reconstruction of Events 7 Full Water Level Measured Water Level Calculated Water Level Water Level Water Injection Calculated Water Temp. Top of Fuel Rack Water Temp Water level highly unlikely to have dropped close to top of fuel rack
8 Unit 1 SFP: Water Chemistry 8 Radio Nuclide Cs-134 Half Life 2 years Unit 1 Skimmer Surge Tank 6/22/2011 8/19/2011 Concentration (Bq/cm 3 ) Unit 1 SFP 2/11/ ,000 18,000 ND Unit 1 T/B 3/26/ E5 Cs years 14,000 23, E5 I days 68 ND ND 1.5E5 Chloride (ppm) 6/22/ /17/ I-131 most likely to have originated from reactor, not SFP (all fuels >1 year after shutdown) Injection of hydrazine for microbes prevention
9 Unit 1 SFP: Structural Integrity Assessment 9 Seismic Response Model Incorporating Damaged Condition Structural Damage Assessment Shear strain from design-basis earthquake confirmed to be within safety limit (5/28/2011)
10 Unit 1 SFP: Condition of Refueling Floor Fuel Handling Machine Rubble Reactor Well Cover Fuel Handling Machine Spent Fuel Pool Surface Fuel handling machine and overhead crane do not seem to have dropped into SFP (Nov. 2014) 10
11 Unit 1 SFP: Next Step 11 Reactor Building Cover (12/4/2014) Schematic of Defueling Structure Reactor building cover to be dismantled to prepare for defueling
12 12 Unit 2 Spent Fuel Pool: Water Injection 4/10/2011 Date (2011) 3/20 3/22 3/25 3/29 3/30 4/1 4/4 4/7 4/10 4/13 4/16 4/19 4/22 4/25 4/28 5/2 5/6 5/10 5/14 5/18 5/22 5/26 5/30 5/31 Injection Volume (ton) < Source Seawater Fresh Water Closed Cycle Cooling FPC system utilized for water injection Injection Method Fuel Pool Cooling System
13 Unit 2 SFP: Closed-Cycle Cooling 13 Stable closed-cycle cooling from 5/31/2011 Injection of hydrazine for anti-corrosion and microbe prevention
14 14 Unit 2 SFP: Reconstruction of Events Full Water Level Measured Water Level Water Level Calculated Water Level Calculated Water Temp. Top of Fuel Rack Measured Water Temp. Water Temp Water level highly unlikely to have dropped close to top of fuel rack
15 Unit 2 SFP: Water Chemistry 15 Radio Nuclide Cs-134 Half Life 2 years Unit 2 Skimmer Surge Tank 4/16/2011 8/19/2011 Concentration (Bq/cm 3 ) Unit 2 SFP 2/10/ , ,000 ND Unit 2 T/B 3/27/ E6 Cs years 150, , E6 I days 4,100 ND ND 1.3E7 Chloride (ppm) 4/16/ /15/ /2/ /30/ I-131 most likely to have originated from reactor, not spent fuel (all fuels >7 months after shutdown)
16 Unit 2 SFP: Water Chemistry (cont d) 16 Chloride (ppm) Cs Removal Reverse Osmosis Ion Exchange Radioactivity (Bq/cc) 11/2011 1/2012 3/2012 5/2012 7/2012 Cl - Cs-137 Cs Water quality steadily improved
17 Unit 2 SFP: Next Step 17 Restorable N Seismic Margin N Initial focus on defueling SFP Y Y Existing R/B Upper Container Full Container Upper Cover Upper Container SFP Core SFP Core SFP Core SFP Core Defueling strategy to be determined after path for core debris retrieval becomes clearer
18 Unit 3 Spent Fuel Pool: Water Injection Japan Self Defense Force Tokyo Fire Department Various attempts to inject water Date (2011) 3/17 3/17 3/17 3/18 3/18 3/19 3/19 3/20 3/22 3/23 3/24 3/25 3/27 3/29 3/31 4/2 4/4 4/7 4/8 4/10 4/12 4/14 4/18 4/22 4/26 5/8 5/9 5/16 5/24 5/28 6/1 6/5 6/9 6/13 6/17 6/26 6/27 6/29 6/30 Injection Volume (ton) Source Seawater Fresh Water Seawater Fresh Water w/ Boron Fresh Water Closed Cycle Cooling Injection Method Helicopter Water Cannon Fire Truck FPC Fire Truck Concrete Pumper FPC 18
19 Unit 3 SFP: Closed-Cycle Cooling 19 Stable closed-cycle cooling from 6/30/2011
20 Unit 3 SFP: Reconstruction of Events Full Water Level Measured Water Level Calculated Water Level Water Level Calculated Water Temp. Top of Fuel Rack Measured Water Temp. Water Temp Water level highly unlikely to have dropped close to top of fuel rack 20
21 21 Unit 3 SFP: Water Chemistry Radio Nuclide Cs-134 Cs-136 Cs-137 I-131 Half Life 2 years 13 days 30 years 8 days Chloride (ppm) 5/8/ ,000 1, ,000 11,000 5/8/ Unit 3 SFP 7/7/ ,000 ND 110,000 ND 4/5/ Concentration (Bq/cm 3 ) 8/19/ ,000 ND 87,000 ND 6/23/ Unit 3 SFP 3/2/2011 ND ND ND ND 8/30/ Unit 3 T/B 4/22/2011 1,500,000 44,000 1,600, , I-131 and Cs-136 most likely to have originated from reactor, not SFP (all fuels >10 months after shutdown) Injection of boric acid to neutralize alkalinity from concrete rubble Injection of hydrazine for anti-corrosion and microbe prevention
22 Unit 3 SFP: Water Chemistry (cont d) 22 Cs Removal Reverse Osmosis Ion Exchange Chloride (ppm) Radioactivity (Bq/cc) 12/2011 2/2012 4/2012 6/2012 8/2012 Cl - Cs-137 Cs Water quality steadily improved
23 Unit 3 SFP: Structural Integrity Assessment Seismic Response Model Incorporating Damaged Condition Structural Damage Assessment Shear strain from design-basis earthquake confirmed to be within safety limit (7/13/2011) 23
24 24 Unit 3 SFP: Rubble Removal End Track Fuel Handling Machine Fuel Rack Pool Liner Fuel Racks Oct. 11 Oct. 12 Remote Control Unit Fuel Rack Information on rubble in SFP obtained by remote-controlled underwater camera (Oct. 2012)
25 Unit 3 SFP: Next Step 25 Spent Fuel Pool Rain Cover Fuel Handling Machine Overhead Crane Refueling Floor (Dec. 2014) Schematic of Defueling Structure Removing rubble from SFP in preparation for defueling
26 Unit 4 Spent Fuel Pool: Water Injection 3/20, water cannon, fresh water, 80 ton Water Injection with Concrete Pumper (3/22/2011) Injection of seawater and fresh water from Mach 20 using water cannons, concrete pumpers, etc. until July 31, /31, Closed Cycle Cooling, fresh water 26
27 Unit 4 SFP: Water Level/Temp. Measurement Fuel Handling Machine Gamma Dosimeter Camera Collecting Water Samples (4/15/2011) Thermocouples Camera Sampling Container Concrete Pumper Concrete pumper used to measure SFP water level/temperature and collect water samples 27
28 Unit 4 SFP: Closed-Cycle Cooling 28 Stable closed-cycle cooling from 7/31/2011
29 Unit 4 SFP: Reconstruction of Events Full Water Level Measured Water Level Assumed 1m drop in level Observation from Helicopter Water Level Calculated Water Temp. Calculated Water Level SFP+well+DS Pit Top of Fuel Rack Measured Water Temp. Surface Temp. Assumed separation between SFP and well Water Temp Lowest water level at top of fuel rack +1.5 m at around April 20,
30 Unit 4 SFP: Reconstruction of Events (cont d) 30 Pre-SBO SBO evaporation SFP level drop Seal pressure drop reactor well to SFP water flow SFP level recovers/equalizes with reactor well level Water from reactor well flowed into SFP during the event
31 Unit 4 SFP: Water Chemistry 31 Radio Nuclide Half Life 4/12/2011 4/28/2011 Unit 4 SFP Concentration (Bq/cm 3 ) 5/7/2011 8/20/2011 Unit 4 SFP 3/4/2011 Unit 4 T/B 3/24/2011 Cs years ND 31 Cs years I days ND ND Chloride (ppm) 4/12/ /20/ /29/ /16/ I-131 most likely to have originated from other reactors, not SFP (all fuels >4 months after shutdown) Injection of hydrazine for anti-corrosion and microbe prevention
32 Unit 4 SFP: Water Chemistry (cont d) 32 Chloride (ppm) 8/2011 Reverse Osmosis Ion Exchange Contamination from reactor well Reverse Osmosis 12/2011 4/2012 8/2012 Cl - (SFP) Cl - (well) Cs-137 Cs-134 Ion Exchange Radioactivity (Bq/cc) Water quality steadily improved
33 Unit 4 SFP: Structural Integrity Assessment Seismic Response Model Incorporating Damaged Condition Structural Damage Assessment Shear strain from design-basis earthquake confirmed to be within safety limit (5/28/2011) 33
34 Unit 4 SFP: Structural Integrity Assessment (cont d) R/B 1st Floor R/B 2nd Floor Optical Measurement Confirmed No Tilting R/B 3rd Floor R/B 4th Floor Schmidt Hammer Testing Confirmed Concrete Strength No Cracks found in SFP Outer Walls Quarterly structural integrity inspection found no issues (since 5/25/2012) 34
35 Unit 4 SFP: Structural Integrity Reinforcement 35 Spent Fuel Pool Steel Pillars Concrete Concrete Shell Wall Additional seismic margin by 20% (7/30/2011)
36 Unit 4 SFP: Progress To Date Pre-work Condition (9/22/2011) Drywell Head Removal (8/10/2012) Defueling Structure Construction (1/14/2013) Completion of Defueling Structure (7/20/2013) Beginning of Defueling (11/18/2013) Successful removal of all fuels from SFP (12/22/2014) 36
37 37 Unit 4 SFP: Inspection of Spent Fuels 8x8 STEP-II STEP-IIIB STEP-IIIB STEP-IIIB Visual Inspection Oxidization Film Thickness Measurement Film Thickness Fuels in Common Pool 8x8 STEP-II Ave. Burnup (GWd/t) STEP-IIIB Inspection of five spent fuels from Unit 4 SFP showed no abnormalities (Nov. 2014)
38 Common Pool 38 Max. Pool Temp. 73 degrees-c Overhead Crane FHM Overhead Crane 3/18/2011: Confirmed pool water level 3/24/2011: Pool cooling restored Radio Nuclide Cs-134 Cs-137 I-131 Half Life 2 years 30 years 8 days Concentration (Bq/cm 3 ) Common Pool 5/13/2011 2/10/ ND 1.2 ND ND ND
39 Dry Cask Storage Facility Inspection results of all 9 dry casks showed no abnormalities (5/30/2013) No Damage of Fuel Bundles or Basket 39
40 New Regulatory Requirements Japan Nuclear Regulation Authority enacted new regulatory requirements effective July
41 Safety Enhancements at Kashiwazaki Kariwa NPS 41 Spray Nozzle Water Level Gauge Spent Fuels FPC Pump Fire Trucks MUWC Pump Condensate Storage Pool Fixed and flexible alternate injection systems with multiple backup power and water sources
42 Safety Enhancements at Kashiwazaki Kariwa NPS (cont d) 42 Water Injection FPC FPC Heat Removal MUWC M/D-FP D/D-FP D/D-FP Filtered Water Tank HX HX RHR Alternate FPC Fire Trucks External Connection Concrete Pumpers Condensate Storage Pool MUWC Alternate RHR Motor-Driven Pumps Diesel-Driven Pumps Multiple layers of defense (only showing safety measures related to SFP)
43 TEPCO s Post-Accident Activities in the U.S. Nuclear Industry Gov t Agencies Global Organizations Academia Professional Organizations, Think Tanks, NPOs, Media Committed to sharing lessons learned; making nuclear power plants safer; carrying out decommissioning safely Hosting Weekly Update Teleconferences 43
44 References 44 TEPCO Website on Decommissioning Status TEPCO Internal Investigation Committee Report (6/20/2012) Main Body Attachment IRID Symposium (7/18/2014) Current Status of Fukushima Daiichi R&D Projects Related to Fuel Debris Retrieval
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