Prof. Dr. Haluk UTKU Institute of Nuclear Sciences Hacettepe University Ankara, Turkey
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Transcript of Prof. Dr. Haluk UTKU Institute of Nuclear Sciences Hacettepe University Ankara, Turkey
Prof. Dr. Haluk UTKUInstitute of Nuclear Sciences
Hacettepe UniversityAnkara, Turkey
PRESSURIZED WATER REACTORS
GENERAL SYSTEM
March 27-28th, 2008, WORLD CONJUNCTURE IN NUCLEAR TECHNOLOGY: Generation III and III+ Nuclear Power Plants, Istanbul
Picture: Mıtsubishi Heavy Industries
REACTOR VESSEL
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REACTOR VESSEL
Height (m) 11.5-13.5
Thickness (mm) 180-255
Internal Diameter (m) 3.4-5.2
Weight (ton) 240-590
Max. Pressure (Atm.) 170
Max. Temperature (oC) 343
Material Manganese Molibdenium Steel (Linen: Stainless Steel, 3.2 mm)
Core Barrel
Vessel Head
Control RodThimble Guide
Coolant Inlet Nozzle
Coolant Outlet
Vessel
Control RodDrive Mechanism
Rod ClusterControl Mechanism
FuelNeutron Reflector
March 27-28th, 2008, WORLD CONJUNCTURE IN NUCLEAR TECHNOLOGY: Generation III and III+ Nuclear Power Plants, Istanbul
REACTOR CORE DIMENSIONS
MWe 600 900 1200 1500
Power (MWth) 1650 2652 3411 4451
Core EquivalentDiameter (m)
2.5 3.0 3.4 3.9
Core ActiveHeight (m)
3.7 3.7 3.7 3.7
Total Fuel Assembly 121 157 193 257
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FUEL
Pictures: GE, Mitsubishi Heavy Ind., Westinghouse
Top CoolantFlow Nozzle
BottomFlow Nozzle
Filter
InstrumentationGuide at the Center
Grid
Control RodGuides
Fuel Rods
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FUELTotal Fuel Assembly* 121 - 257
Assembly Lattice 14x14 – 17x17
Distance Between Fuel Rodsin an Assembly(cm)
0.31 cm
Fuel Rod Diameter (cm) 0.94
U-235 enrichment (%) 1.9 – 4.95
Core Total Fuel Weight (ton) 89 - 121
Burnup (MWd/MTU) 33000 - 60000
* For a reactor with 193 fuel assambly there are 51000 fuel rods and approximately 18 million fuel pelets.
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FUEL FAILURE RATES IN US PLANTS
CONTRIBUTION OF FUEL CYCLE TO POWER GENERATION COST
Maintenance-Operation+Investment Fuel Cycle
Natural Uranium and Processing (%2.6)
Enrichment (%3.6)
Production of Fuel Assembly (%2.6)
Disposal (%11.2)
%20%80
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Ractor Vessel
PressurizerSteamGenerator
CoolantPump
Reactor Coolant Pressure (Atm.)Secondary System Presssure (Atm.)
~153~ 60
Coolant Flow Rate (m3/h/loop) 2.01x104 for 3420 MWth
2.58x104 for 4450 MWth
Pump Shaft Power (kW)ΔP (Atm.)
4470 – 74606
Coolant Inlet Temperature (oC)Coolant Outlet Temperature (oC)
~ 288~ 328
REACTOR CORE COOLANT SYSTEM
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Coolant Pump
Coolant Pump - Pressurizer
Pressurizer
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•Recirculating Steam Generators:Westinghouse-USA; Mitsubishi Heavy Industries-Japan; Siemens-Kraftwerke-Germany; Babcock & Wilcox-Canada•Once-Through Steam Generator:Babcock & Wilcox, USA•Horizontally Placed Steam Generators:Zio, Atommash-Russian; Vitkovice-Check
STEAM GENERATORS
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Primary Inlet Primary Outlet
Steam Outlet
Steam Separators
Feedwater Inlet
Downcomer Annulus
Tube Sheet
Tube Supports
Tube Bundle
RECIRCULATING STEAM GENERATORS
References:www.kntc.re.kr
March 27-28th, 2008, WORLD CONJUNCTURE IN NUCLEAR TECHNOLOGY: Generation III and III+ Nuclear Power Plants, Istanbul
ONCE-THROUGH AND HORIZONTAL STEAM GENERATORS
Reactor coolant flow tubesı
From Reactor
To Reactor
Perforated plates
To Turbine
Steam Generator
Pressure 63 Atm.Feedwater Temp. 220-225 oCMoisture at the outlet 0.2%
CONTAINMENT BUILDING
Containment Design relies on calculating the peak containment pressure during potential accidents. The containment must withstand the pressure and temperature of Design Basis Accident without exceeding the design leakage rate of 0.2% volume/day for the 24 hours and 1% volume/day thereafter. Steel linen is used inside to protect from any gas diffusion.Applied Regulations:10 CFR 50, Appendix A, General Design Criteria 52, 53 and 54 10 CFR 50, Appendix J
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CONTAINMENT BUILDING
Sandia National Laboratories, USA conducted a test of slamming a jet fighter into a large concrete block at 775 km/h airplane left a 6.4 cm deep gouge in the concrete. Although the block was not constructed like a containment building missle shield, the results were considered indicative.In another work EPRI, Electric Power Research Institute, conducted a aircraft crash impact analysis. Analysis showed that no parts of the aircraft entered the containment buildings. The robust containment structure was not breached (Boeing 767-400, weights 203 tons with full fuel, the wing span is 51.5 m.)
March 27-28th, 2008, WORLD CONJUNCTURE IN NUCLEAR TECHNOLOGY: Generation III and III+ Nuclear Power Plants, Istanbul
• Decay heat removal system after shutdown• Residual heat removal system• Emergency core cooling cystem• Containment spray system• Radiation control systems• Systems to filter accumulated gas in the
containment
ENGINNERING SAFETY FEATURES
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Relative deviation from the criticalitiy is called reactivity.
1. Shutdown Rods2. Gray Rods3. Dark Rods4. Xenon5. Fuel Temperature reactivity feedback6. Moderator (Coolant) Temperature & boron reactivity feedback
Note that reactivity is a computed parameter, and not a measured parameter. It is not directly available at an actual plant.
THE REACTIVITY CONTRIBUTIONS OF DEVICES AND PHYSICAL PHENOMENON
March 27-28th, 2008, WORLD CONJUNCTURE IN NUCLEAR TECHNOLOGY: Generation III and III+ Nuclear Power Plants, Istanbul