1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)
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Transcript of 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)
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BySohail Ejaz Abbasi and Tasneem Fatima
Karachi Nuclear Power Plant (KANUPP)
CANDU Reactor
In operation since 1972
Under water storage of spent fuel bundles in spent fuel storage bay
Completed 30 years design life in the year 2002
By refurbishment & safety upgrades, KANUPP operational life extended up to 2019
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11 spent fuel bundles stored in one storage tray
Storage Layout : 120 stacks of trays each consisting of 18 tiers of trays
Design Storage capacity: 23,760 spent fuel bundles
Total Water Depth : 5.94 m
Water Shield thickness: 3.96 m
8.7E-3 mSv/hr is maintained at 30.5 cm (1 foot) above the water surface
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The KANUPP SFB is divided into four areas.
Storage area Inspection area Shipping cask area Decontamination area
Designed for 20 years of operation with 80% capacity factor
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Almost complete its design capacity
Current SFB Inventory ~ 23151 spent fuel bundles (up to 1st January, 2010)
A dry storage facility is being planned as an ultimate solution of storage problem
An alternate short term remedy is to enhance the storage capacity of existing SFB
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Increase in no. of layers / stack
Place cooler bundle tray at top of stack
Reserve space for handling / storage of freshly discharged bundles
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Computation of thickness of water column for shielding
Analysis of cooling capacity of bay water
Criticality assessment
Seismic Analysis
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Evaluation of Source Term Source term of spent fuel bundles is
evaluated by employing ORIKAN computer code (modified version of ORIGEN 2 for KANUPP core)
The maximum value of 9000 MWD/TeU is selected as representative burnup
It provides envelope for all average discharge burnup variations
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Shielding Calculations Contribution of all spent fuel bundles
stored in storage bay is modeled
The rate of decrease of activity & decay heat of spent fuel is very fast within 10 years of cooling time; slows down after wards
10 years cooling period is considered in the shielding Calculations
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More than 72% of total spent fuel bundles have cooling time greater than 10 years
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2.13m water column thickness is sufficient to maintain required dose rate ~ 8.7E-3 mSv/hr
The active height of stack with 24 fuel trays is about 2.44 m
3.51 m water column is still available to shield the spent fuel
The dose rate with 3.51m water column comes out as 2.8E-6 mSv/hr
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Dose rates due to 10 years, 5 years and 1 year cooled spent fuel bundles are tabulated as:
Dose Rates (mSv/hr) w.r.t. various cooling periods at available shield thickness
Cooling Period (Years)
Dose Rates (mSv/hr)
Available Water Shield Thickness (m)
3.51 3.20
10 2.78E-06 4.35E-06
5 6.09E-05 7.22E-05
1 1.22E-03 1.48E-03
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Design total heat removal capacity of bay cooling system is 1.8 MWth
0.21 MWth decay heat will be generated in the spent fuel storage bay due to overall 31680 spent fuel
0.27 MWth decay heat is calculated due to unloading of in-core fuel bundles (assuming 3 months cooling)
The calculated total decay heat 0.48 MWth is well in limits of design heat removal capacity of bay cooling system
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The spent fuel placed in HDTR in proposed layout in the spent fuel storage bay will remain subcritical in operational and accidental conditions
Use of steel in spent fuel trays, racks and liner in the surrounding walls of the bay make Keff even lesser
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A seismic analysis enabled to assess the stability against seismic event (ground acceleration 0.2g)
The result of analysis reveals that overturning will not take place under the specified seismic loading
Sliding will take place, however much less than the clearance available b/w two adjacent racks or between a rack and bay wall
Stress analysis ensured that the axial, bending and shear stresses are within the allowable limits
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Storage capacity of SFB enhanced by increasing tray stack height from 18 layers to 24
Seismic stability will be attained by placing these trays in a “High Density Tray Rack”
Two columns each consisting of 24 layers of trays will be loaded into one rack
60 racks could be arranged in layout of 10 x 6 in the storage area of SFB
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Each rack will hold 528 spent fuel bundles
7920 more spent fuel can be stored
Overall 31680 spent fuel can be accommodated
The development and implementation of HDTR System at KANUPP will enhance 1/3rd of design storage capacity
Expected to get relief by mid of 2017 assuming 72% RP and 75% availability factor
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Parameters Existing Storage Enhanced Storage (HDTR System)
Single Storage Unit in Bay 18 Fuel Trays Stack 48 Fuel Trays Rack (2 x 24 trays)
Number of Bundles in Single Unit
198 528
Array in Bay 12x10 10x6
Number of Bundles in Bay 23760 31680
Fuel Storage Advantage (%) - 33.3
Available Water Shielding (cm) 396 351
Seismic Qualification (0.2 Ground Acceleration)
Not Qualified Qualified
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The high density tray rack is a seismically and structurally qualified stainless steel frame to be placed in storage area of spent fuel storage bay.
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The HDTRs placement in the spent fuel bay and tray loading operation has been commenced in the month of April 2010
At first step, five adjacent stacks of trays were transferred from their storage position to the inspection area
By using service building hatch and crane, a rack was brought into the shipping cask loading area of spent fuel storage bay
The bay crane picked the rack and placed in the predefined location in the storage area
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12 spent fuel trays with least cooling period were loaded at the bottom of the rack; six in each column of the rack
These trays were covered by loading 22 – 23 years cooled 36 trays; 18 trays in each column
Two high density tray racks have been successfully loaded so far in the presence of the IAEA Safeguards inspectors
Two more HDTRs will be filled during forthcoming IAEA Safeguards inspection
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KANUPP fuel is under IAEA Safeguards High density tray rack and its top cover
have been designed to facilitate the provision for IAEA safeguards seal
Two seals have been incorporated on to the top cover of each rack by the IAEA safeguards inspectors
Clearance ~ 100 mm b/w two adjacent racks and b/w rack & bay wall will be available to accommodate the Collimator used for annual spent fuel verification measurement carried out by IAEA inspectors
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By implementing HDTR system, the storage capacity of KANUPP SFB would be enhanced for about 7920 more spent fuel bundles
Augmentation in bay storage capacity will provide the enough time to build an interim spent fuel dry storage facility for KANUPP
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To achieve ultimate solution for spent fuel storage space problem in existing bay, an interim spent fuel dry storage facility has been planned to construct within plant premises
Operation of HDTR will be stopped, once the dry fuel storage facility would be operational
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THANKS
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