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1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 1: 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)

Page 2: 1 By Sohail 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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Page 3: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 4: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 5: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 6: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 7: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 8: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

Computation of thickness of water column for shielding

Analysis of cooling capacity of bay water

Criticality assessment

Seismic Analysis

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Page 9: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 10: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 11: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 12: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 13: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

More than 72% of total spent fuel bundles have cooling time greater than 10 years

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Page 14: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 15: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 16: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 17: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 18: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 19: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 20: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 21: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 22: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 23: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 24: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 25: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 26: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 27: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 28: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 29: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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Page 30: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 31: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 32: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

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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Page 33: 1 By Sohail Ejaz Abbasi and Tasneem Fatima Karachi Nuclear Power Plant (KANUPP)

THANKS

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