Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant
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(2) European Lead-cooled Fast Reactor ELFR KEY DESIGN GUIDELINES Sustainability of the fuel cycle. Waste minimization and management. Economics. Simpler design solutions/Lower life cycle cost. Safety and reliability. Passive – no offsite emergency response required. Proliferation resistance. Fuel bearing MAs. ELFR KEY DESIGN PARAMETERS Power 1500 MW(th), 600 MW(e) Thermal efficiency ~42% Core diameter 4.5 m Core height 1.4 m Core fuel MOX (1st load) Coolant temperature 400/480 oC Maximum cladding temperature. 550 oC. Core breeding ratio (CBR). ~1. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 2.
(3) European Lead-cooled Fast Reactor: Adiabatic Reactor concept. The ELFR enables the closure of the fuel cycle. • Multiple Recycling of the long-lived and high radiotoxicity wastes. • Discharge of the sole fission products (500 kg/year) for a simplified storage (decay: 400 years ). • Fabrication of fresh fuel only by addition of natural Uranium Ǧusing 1/100 of current usage- or addition of depleted Uranium Ǧwithout affecting the current resources-. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 3.
(4) ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) ALFRED KEY PARAMETERS AND COMPONENTS LAYOUT. Power. 300 MW(th), ~120 Mw(e). Thermal efficiency Primary system. ~42% Pool type, compact. Primary coolant. Coolant temperature Primary system pressure loss (at power) Primary coolant circulation for DHR. Fluid. Pure lead. Circulation at power. Forced (mechanical pumps). Emergency circulation. Natural circulation. 400/480 oC < 1.5 bar Natural circulation MOX (1st load). Fuel Fuel cladding material Steam Generators. 15-15/Ti as a reference 8 or 4 , integrated in the main vessel. Secondary cycle. Water-superheated steam at 180 bar, 335-450 oC. Primary pumps. 8 or 4, mechanical, integrated in the Steam Generators, suction from hot collector. Internals. All internals removable. Inner vessel. Cylindrical. Hot collector. Small-volume, enclosed by the Inner Vessel. Decay Heat Removal. Industrial/Intellectual property of Ansaldo Nucleare SpA. 4 independent, redundant and passive DHR systems, 3 out of 4 loops of each system are capable of removing the decay heat. International CAE Conference, October 19/20, 2015. 4.
(5) ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator). Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 5.
(6) Primary Pump: Analysis of Alternatives Option A: pull the coolant via blade pump. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 6.
(7) Primary Pump: Analysis of Alternatives Option B: push the coolant Architectural layout. Pump duct. Steam generator Core Pressure chamber. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 7.
(8) Primary Pump: Analysis of Alternatives Option B/1: push the coolant via jet pump. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 8.
(9) Primary Pump: Analysis of Alternatives Option B/2: push the coolant via screw pump. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 9.
(10) Screw pump: Governing equations. • •. Conservation of mass ሶ ൌ ࣋ כ ࢂ כൌ ࢉ࢙࢚ࢇ࢚ Conservation of energy absolute reference frame. ̴࢚࢚ࢇ࢈࢙ ൌ ࢉ࢙࢚ࢇ࢚ ௧௧̴̴௦̴௨௧ ൌ ௧௧̴௦̴ ͳ ͳ ଶ ଶ ௨௧ ܸ כ ߩ כ௨௧ ൌ ௧ ܸ כ ߩ כ ʹ ʹ relative reference frame. •. ̴࢚࢚࢘ࢋ ൌ ࢉ࢙࢚ࢇ࢚ ௧௧̴̴̴௨௧ ൌ ௧௧̴̴ ͳ ͳ ଶ ଶ ௨௧ ܹ כ ߩ כ௨௧ െ ܷ כ ߩ כ௨௧ ʹ ʹ ͳ ͳ ଶ ଶ ൌ ௧ ܹ כ ߩ כ െ ܷ כ ߩ כ ʹ ʹ Conservation of angular momentum ࡸ࢙ ൌ ࢁ࢛࢚ ࢚࢛࢚࢜ כെ ሺࢁ ࢚࢜ כሻ. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 10.
(11) Screw pump: absolute vs reference frame. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 11.
(12) Screw pump: degrees of freedom RPM. Convergent bulb length. D_hubin_screw. Bladed divergent length Divergent bulb length. D_hubout_screw. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 12.
(13) Screw pump: BCs. Total pressure Mass flow rate (imposed as BC). Output of simulation. Mass flow rate Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 13.
(14) Screw pump: stationary vs rotating domain. Stationary domain S. Rotating domain R. Frame change: Frozen rotor. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 14.
(15) Reference case: 280 RPM, non viscous. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 15.
(16) Reference case: 280 RPM, non viscous. 400000 350000. Static pressure [Pa]. 300000 250000 200000 150000 theoretical analysis. 100000. non viscous CFD simulation 50000 0 0. 1. 2. 3. 4. 5. Pump height [m]. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 16.
(17) Reference case: 280 RPM, viscous. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 17.
(18) Reference case: 280 RPM, viscous. 500000 450000. Total pressure [Pa]. 400000 350000 300000 250000 200000 150000. non-viscous CFD simulation. 100000. viscous CFD simulation. 50000 0 0. 1. 2. 3. 4. 5. Pump height [m]. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 18.
(19) Reference case: 280 RPM, viscous - Pressure losses at locked rotor conditions. Pressure losses at pump off. mass flow rate = 644,7 [kg/s] (10% of nominal mass flow rate) Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. differential pressure = 0,04 [bar] 19.
(20) Improved design: 315 RPM, geometrical adjustments. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 20.
(21) Improved design: 315 RPM, geometrical adjustments 2.50E+05. 315 RPM, improved geometry. Differential total pressure [Pa]. 2.00E+05. 1.50E+05. 280 RPM 1.00E+05. 5.00E+04. 0.00E+00 1500. 2500. 3500. 4500. 5500. 6500. 7500. 8500. 9500. Mass flow rate [kg/s]. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 21.
(22) Conclusions and future work. • The ANSYS CFX 3D simulations confirm the results of the theoretical analysis. • The improved design of the screw pump delivers the required ݉ሶand ο, keeping velocities within acceptable values. • ANSYS CFX has shown a significant ease of use, stability and effectiveness.. • The next step is the integration of the screw pump in the overall system. Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 22.
(23) Final remarks. “ALFRED will represent the first time that a critical heavy liquid metal cooled reactor would provide electricity to the grid” Strategic Research and Innovation Agenda (February 2013). Industrial/Intellectual property of Ansaldo Nucleare SpA. International CAE Conference, October 19/20, 2015. 23.
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