BWR Description Jacopo Buongiorno Associate Professor of Nuclear Science and Engineering
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1 BWR Description Jacopo Buongiorno Associate Professor of Nuclear Science and Engineering 22.06: Engineering of Nuclear Systems 1
2 Boiling Water Reactor (BWR) Public domain image by US NRC. 2
3 The BWR is a Direct Cycle Plant Core Steam line Reactor vessel Recirculation pumps Separators & dryers Feedwater Heater Turbine generator Feed pumps Demineralizer Condensate pumps Image by MIT OpenCourseWare. System pressure, MPa Core thermal power, MW th 3323 Electric power, MWe 1130 Thermal efficiency, % 34 Vessel ID / Thickness / Height, m 6.4 / 0.16 / 22 Core shroud diameter, m 5.2 Number of fuel assemblies 764 Core mass flow rate, kg/s Core inlet temperature, ºC Core outlet temperature, ºC Core exit quality, % 13.1 Feedwater flow rate, kg/s 1820 Feedwater temperature, ºC 220 Steam flow rate, kg/s 1820 Steam temperature, ºC Core power density, kw/l 50.5 Core flow bypass 14 % A.V. Nero, Jr., A Guidebook to Nuclear Reactors,
4 Phase Diagram of Water Pressure [MPa] Saturation line Liquid BWR core Vapor Temperature [ C] 4
5 BWR Core 5
6 BWR Core Layout 0 Fuel Bundle Control Cell Bundle Peripheral Bundle Control Blade Typical Control Cell Core Layout source unknown All rights reserved. This content is excluded from our Creative Commons license. For more information, see 6
7 BWR Fuel Assembly Upper Tie Plate Channel Fastener Assembly Fuel Cladding Fuel Claddding Expansion Spring Fuel Channel Plenum Spring Lower Tie Plate Nose Piece Fuel Pellet Fuel Rod Single bundle 3D view Image by MIT OpenCourseWare. source unknown All rights reserved. This content is excluded from our Creative Commons license. For more information, see P07.cvs Fuel l assemblies have h a duct d t wall to t prevent vapor radial drifting 7
8 BWR Fuel Assemblies Image by MIT OpenCourseWare. 8
9 Fuel Assembly Parameters for 9x9 Fuel Assembly Parameter Value Fuel Pellet OD (mm) 9.55 Fuel Pin OD (mm) Clad Thickness (mm) 0.71 Fuel Pin Pitch (mm) Active Fuel rod height (mm) Total Fuel Rod height (mm) Part Length Rod Height (mm) 2436 Fuel Pins / Water Rods per Fuel Assembly 74/2 Number of Part Length Rods 8 Inner/Outer diameter of the water rods (mm) 23.37/24.89 Duct Thickness (mm) 2.54 Clearance between duct and peripheral fuel rods (mm) 3.53 Clearance between water rods and fuel rods (mm) 1.79 Assembly Outer Dimension (mm) Inter-Assembly Gap (mm) Average Linear Power (kw/m) Pressure Drop (kpa) 160 Average enrichment (wt%) 4.31 Average Discharge Burnup (GWd/t) 56 Refueling scheme 4 batches Number of rods with gadolinia 8 Gadolinia concentration (wt%) 5 Hydrogen to Heavy Metal Ratio Void Coefficient (pcm/% void) -144 Fuel Temperature Coefficient (pcm/k) -1.7 Approximate Assembly Weight (kg) 281 9
10 Control Blade Image removed due to copyright restrictions. Image by MIT OpenCourseWare. 10
11 BWR Control Rod Drive System Image by MIT OpenCourseWare. 11
12 BWR SPATIAL CORE PROPERTIES (WITH CONTROL RODS PARTIALLY INSERTED) 1.5 Relative power Average void fraction Critical heat flux ratio in hot channel x0.1 Relative parameters Bottom of core Relative axial length Top of core Image by MIT OpenCourseWare. 12
13 POWER IN FRESH FUEL ASSEMBLY AS ADJACENT CONTROL ROD IS WITHDRAWN TOWARD BOTTOMO Relative Power Percent Full Insertion (Bottom) Nodal power normalized to 1.0 over the core. Axial Length of Fuel (Top) Image by MIT OpenCourseWare. BWR/6: General Description of a BWR, GE,
14 Connection of BWR Core Design to Neutronics Why are the fuel rods spaced out more in a BWR than in a PWR? Why is the core power density lower in a BWR core than in a PWR? What is the purpose of spatial fuel enrichment zoning throughout a BWR fuel assembly? What function do the water rods perform? Why are the BWR control rods inserted df from the bottom of the core? Can dissolved boron be used as a means to control reactivity in a BWR core? 14
15 BWR Bundle Design Advances Extended burnup features More fuel pins (10 10)) for a lower heat flux Heavier fuel loadings Control Rod Improved mechanical performance Barrier cladding Low growth, wear resistant materials Improved operational performance performance Natural uranium blankets Flow mixing grids to enhance margin to critical power Part-Length Fuel Rods (Stability, SDM) Large Central Water Channels (Stability, y,sdm ) ( Sophisticated poison & enrichment zoning Fuel Rod Part Length Fuel Rod Image by MIT OpenCourseWare. source unknown All rights reserved. This content is excluded from our Creative Commons license. For more information, see 15
16 BWR Vessel and Vessel Internals 16
17 BWR Vessel Large vessel made of ring forgings to avoid welds in the core region Vessel bottom head accommodates CR penetrations From: L.E. Fennern, ABWR Seminar Reactor, Core & Neutronics. April 13, ABWR RPV beltline forging, weight: 127 tons; dimensions: 7.48 m outside diameter, 7.12 m inside diameter, 3.96 m high; material: ASME SA 508, Class 3 EQ. source unknown. All rights reserved. This content is excluded from our Creative Commons license. For more information, see 17
18 BWR Vessel Internals From: V. Shah, P. MacDonald, Aging and Life Extension of Major LWR Components, Elsevier. All rights reserved. This content is excluded from our Creative Commons license. For more information, see Source: Shah, V. N. and P. E. MacDonald. Aging and Life Extension of Major Light Water Reactor Components. Atlanta, GA: Elsevier Science, ISBN:
19 Steam Separators Steam Dryers Dryer Height Steam Dome From: V. Shah, P. MacDonald, Aging and Life Extension of Major LWR Components, Drain Pipes Steam + Droplets Elsevier. All rights reserved. This content is excluded from our Creative Commons license. For more information, see Source: Shah, V. N. and P. E. MacDonald. Aging and Life Extension of Major Light Water Reactor Components. Atlanta, GA: Elsevier Science, ISBN:
20 BWR Recirculation System 20
21 BWR Recirculation System BWR/6 ABWR ESBWR Steam Dryers Steam Separators Driving Flow Steam Flow to Turbine Feed Flow from Condenser Core Jet Pump Recirculation Pump External recirculation Ten internal Relies on natural pumps + jet pumps recirculation pumps circulation Courtesy of GE Hitachi Nuclear Systems. Used with permission. 21
22 Traditional BWR vs ABWR and ESBWR Parameter BWR/4-Mk I (Browns Ferry 3) BWR/6-Mk III (Grand Gulf) ABWR ESBWR Power (MWt/MWe) 3293/ / / /1550 Vessel height/dia. (m) 21.9/ / / /7.1 Fuel bundles (number) Active fuel height (m) Power density (kw/l) Recirculation pumps 2(large) 2(large) 10 Zero Number of CRDs/type 185/LP 193/LP 205/FM 269/FM Safety system pumps Zero Safety diesel generator Zero Core damage freq./yr 1E-5 1E-6 1E-7 1E-7 Safety Bldg Vol (m 3 /MWe) <100 Image by MIT OpenCourseWare. 22
23 BWR/6 Recirculation Flow 1 unit Steam Dryers Steam Separators Driving Flow Core Steam Flow to Turbine 1 unit 5 units Feed Flow from Turbine 1 unit 4 units Jet Pump Recirculation Pump 6 units 2 units Jet Pump M-Ratio = Suction Flow / Drive Flow = 2 Courtesy of GE Hitachi Nuclear Systems. Used with permission. 23
24 BWR Recirculation Pumps Image removed due to copyright restrictions. Elsevier. All rights reserved. This content is excluded from our Creative Commons license. For more information, see 24
25 BWR Jet Pumps Holddown Assembly Inlet Jet Pump Nozzle Assembly Restrainers and Supports Core Shroud Mixer Restrainers and Supports Inlet Riser Reactor Vessel Wall Core Support Diffuser and Tail Pipe Recirculation Inlet Nozzle 1 per Jet Pump Riser Elsevier. All rights reserved. This content is excluded from our Creative Commons license. For more information, see 25
26 BWR Balance Of Plant (BOP) 26
27 BWR Power Cycle Steam Moisture Separator and Reheater Reactor Vessel Separators and Dryers Feedwater Extraction Steam Turbine HP LP Condenser LP Generator Core Demineralizers Recirc Pump Recirc Pump Feed Pumps Extraction Steam Heaters Condensate Pumps Drain Pumps Heaters Courtesy of GE Hitachi Nuclear Systems. Used with permission. BWR/6, General Description of a BWR, GE,
28 Radioactive Steam Entire Power Conversion System becomes Radioactive Shielding is Needed d Reaction products from water: O 16 + n N 16 + H 1, T 1/2 = 7.2 s;, O 17 + n N 17 + H 1, T 1/2 = 4.2 s;, O 18 + n O 19 F 19, T 1/2 = 29 s;, Activation of corrosion products: Fe 54 + n Fe 55, T 1/2 = 2.7 y; Fe 58 + n Fe 59, T 1/2 = 44.6 d;, Co 59 + n Co 60,T = 5.3 y;, Ni 58 + n Ni 59 1/2, T 1/2 = 8x10 4 y;, Ni 62 + n Ni 63, T 1/2 = 100 y;, 28
29 Air Ejector Removes Any Gases in Coolant Downstream of Condenser They Must be Held Up and Stabilized Nobel Gas Fission Products Escaped from Faulty Fuel Pins (Xe, Kr isotopes) Xe 135 Cs b - + g, T 1/2 = 9.2 h Kr 88 Rb 88 + b - + g, T 1/2 = 2.8 h Kr 85 Rb 85 + b -1 + g, T 1/2 = 10.7 y H 2 from Radiolysis of H 2 O N Isotopes Produced by (O + n) Reactions Gases Leaking into Condenser 29
30 BWR safety systems and containment to be discussed later in the course 30
31 MIT OpenCourseWare Engineering of Nuclear Systems Fall 2010 For information about citing these materials or our Terms of Use, visit:
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