Overview of Mitsubishi Advanced PWR
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IAEA INPRO 7th Dialogue Forum in Vienna Overview of Mitsubishi Advanced PWR November 19, 2013 Sumio FUJII Acting General Manager, Nuclear Systems Engineering Department © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 Remarks on proprietary and copyright information • The data and information in the presentation materials are proprietary of Mitsubishi Heavy Industries. • Utilization of the data and information is limited to the purpose of INPRO 7th Dialogue Forum. • The data and information concerning advanced PWR in the presentation materials are never permanent. They may be changed in the process of nuclear power plant construction for individual site. • Mitsubishi Heavy Industries has the copyright of all figures and photos in the presentation materials. © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 1 Contents 1. Development History of Mitsubishi PWR 2. Advanced PWR for Global Deployment 3. Safety of Mitsubishi Advanced PWR 4. State-of-Art Technology for Digital Instrumentation & Control System of Mitsubishi Advanced PWR 5. Safety Enhancements for Beyond Design Basis Accident of Mitsubishi Advanced PWR 6. Construction Management of Mitsubishi Advanced PWR 7. Operation and Maintenance Management of Mitsubishi Advanced PWR 8. Conclusion © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 2 Development History of Mitsubishi PWR © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 3 Line-up of Mitsubishi PWR for Japanese utilities 2Loop (((300-600MWe ))) 3loop (((900-1000 MWe ))) 4Loop (((1200-1500MWe ))) Unit C/O Outpt Unit C/O Output Unit C/O Output Ohi1 1979.03 1175 MkWe Mihama1 1970.11 340 MkWe Takahama1 1974.11 826 MkWe Ohi2 1979.12 1175 MkWe Mihama2 1972.07 500 MkWe Takahama2 1975.11. 826 MkWe Turuga2 1987.02 1160 MkWe Genkai1 1975.10 559 MkWe 1976.12 Mihama3 826 MkWe Ohi3 1991.12 1180 MkWe Ikata1 1977.09 566 MkWe Sendai1 1984.07 890 MkWe Ohi4 1993.02 1180 MkWe Genkai2 1981.03 559 MkWe Takahama3 1985.01 870 MkWe Genkai3 1994.03 1180 MkWe Ikata2 1982.03 566 MkWe Takahama4 1985.06 870 MkWe Genkai4 1997.07 1180 MkWe Tomari1 1989.06 579 MkWe ~ Senfai2 1985.11 890 MkWe Tsuruga3 201X 1538 MkWe Tomari2 1991.04 579 MkWe Tsuruga4 201X~ 1538 MkWe Ikata3 1994.12 890 MkWe Tomari3 2009.12 912 MkWe Tsuruga 3 & 4 are Advanced PWRs. © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 4 Development of Advanced PWR (J-APWR) • The development of the Advanced PWR (APWR) was started in late 1980s as a joint cooperative development project by five Japanese PWR owner utilities and Mitsubishi Heavy Industries (MHI), financially supported by the Ministry of International Trade and Industry (Currently the Ministry of Economy, Trade, and Industry) as a part of the Phase III Improvement and Standardization Program of Japanese PWR. • The design of the APWR was based on MHI’s conventional 4-loop plant technologies, on which MHI has accumulated significant operating experiences, and was scaled up to achieve higher electrical output. • In addition to adopting those proven technologies after the first step development, further modifications were also made on the prototype APWR design to improve economy, safety, reliability, operability, and maintainability by incorporating advanced technologies. • The first APWR plant (Japanese APWR) is Tsuruga-3 producing 1538 MWe operated by the Japan Atomic Power Company. The Tsuruga-3 is now under safety review for construction permission, which got suspended due to the Fukushima Daiichi accident. © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 5 GⅢ+ Reactors Development 70’s 80’s 90’s 2000’s 2010’s 2020’s Development & Improvement of PWR Technology APWR Tsuruga 3, 4 licensing process Enhanced up to APWR US-APWR US Utilities US NRC Licensing Comanche Peak 3, 4 European Utilities EU-APWR European and ATMEA1 Global Utilities AREVA by ATMEA (Joint Venture) © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 6 Development of US-APWR & EU-APWR • By referring the J-APWR, MHI has designed the US-APWR which meets regulatory requirements in United States of America as well as Utilities Requirements Document (URD). The turbine-generator system and all electric equipment of the US-APWR are designed for 60 Hz electric grid. • Basic designs of the US-APWR except for the fuel length are same as those of the J-APWR whose design has completed. The US-APWR has been developed as a larger-output version of the J-APWR, aiming at higher electrical outputs and improved economics, by modifying some design features mainly in the secondary side without increasing core thermal output. • The fuel length was changed to 4.2 meters in place of 3.66 meter, and the electric output was increased to about 1700 MWt. • EU-APWR is a sister plant of the US-APWR and is aiming to satisfy European Utilities Requirements (EUR). Nevertheless the turbine- generator system and all of electric equipment are designed as 50 Hz, designs of core and other major equipment on the reactor coolant system are same as those of the US-APWR except the reactor coolant pumps. © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 7 Advanced PWR for Global Deployment © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 8 US-APWR & EU-APWR : Course of Design A course of design for the US-APWR and EU-APWR is to; To achieve the best performance in safety, reliability, operability, and maintainability by incorporating advanced technologies. To provide the world’s largest NPP for large electric grid utilities aiming at economical production costs. To contribute toward safe, stable and flexible power production through satisfying American “Utilities Requirements Document ” and “ European Utilities Requirements ”. © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 9 Major Features on safety and reliability V Top-mounted ICIS for avoiding penetrations at the RV bottom V Full 4-train safety systems with b est-mix of passive SH SH and active systems, which RV allows o n-power SH ACC ACC SH maintenance RWSP V Full digital I&C technology enabling one-man operation © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 10 Major Features on economy V Large reactor producing thermal output of 4,466MWt V 14-ft fuels creating additional thermal margin and flexible core operation V 14-ft fuels making 24-month operation without deterioration in fuel economy V Enhanced SG heat transfer performance by enlarged heat transfer area with triangular lattice arrangement of SG tubes V High-performance s team-water separators generating high quality steam in SG V High performance LP-turbine having last stage blades of 70 inches length V Secondary system enabling high thermal efficiency over 36% © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 11 Comparison of Major Specifications © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 12 Reactor Vessel and Internals © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 13 Reactor Core Reactor Vessel Core design Control rod drive mechanism Outlet nozzle Inlet nozzle Fuel assembly Reactor Fuel and Rod cluster control assemblies vessel A, B, C, D : Control group bank SA, SB, SC, SD : Shutdown group bank © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 14 Major Core Parameters Best estimates Design limits of initial core Active Core Active core equivalent diameters (cold) 3.89 m Active fuel height (cold) 4.2 m Hydrogen/Uranium atomic ratio (cold) 5.57 Core average linear power density 15.2 kW/m Maximum linear power density 39.5 kW/m 31.2 kW/m N Nuclear enthalpy rise hot channel factor F ∆H 1.73 1.50 Delayed neutron fraction βeff (%) 0.44 to 0.75 0.50 to 0.69 Prompt neutron lifetime, l* (µsec) 8 to 20 14.0 to 15.3 Reactivity coefficient Doppler power coefficient (pcm/%power) BOC -12.4 to -7.4 EOC -12.1 to -7.6 Moderator temperature coefficient (pcm/ ℃℃℃) -71.1 to -1.4 Moderator density coefficient (pcm/g/cm 3) < 0.51x10 5 < 0.32x10 5 Boron coefficient (pcm/ppm) - -9.3 to -8.0 Neutron multiplication factor Maximum core reactivity keff (BOC,cold,noXe) - 1.223 Maximum fresh fuel assembly k∞ - 1.456 Boron concentration (ppm) Refueling boron concentration > 4000 - Cold shutdown, BOC, noXe, ARI, keff <0.95 - 1850 Cold shutdown, BOC, noXe, ARO keff =0.99 - 1796 Hot shutdown, BOC, noXe, ARO keff =0.99 - 1706 Hot zero power, BOC, noXe, ARO keff =1.0 - 1579 Hot full power, BOC, noXe, ARO keff =1.0 - 1444 Hot zero power, BOC, equilibrium Xe, ARO - 1086 Shutdown margin BOC 2.94 > 1.6 EOC 2.15 © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 8AS-EXP-20130003 15 Major Thermal-Hydraulic Parameters Design Parameters Design Values Coolant condition Primary coolant system pressure (MPa(absolute)) 15.51 Thermal design flow rate (ton/hr) 76,300 Effectiveflowrateforcorecooling(ton/hr) 69,500 Reactor vessel inlet temperature (℃) 288.1 Average rise temperature in reactor vessel (℃) 36.9 Heat transfer at normal condition Fraction of heat generated in fuel (%) 97.4 Core average linear heat rate (kW/m) 15.2 Maximum local peak linear heat rate at FQ=2.6(kW/m) 39.5 Power density (kW/l) 89.2 Specific power (kW/kg uranium) 32.0 Minimum DNBR by WRB-2 correlation At nominal condition; for typical hot channel 2.05 for thimble hot channel 1.98 During AOO; for typical hot channel > 1.35 for thimble hot channel > 1.33 Maximum fuel centerline temperature during AOO (℃℃℃) < 2548 © 2013 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.