ABWR Reactor Technology

Transcription

1 9 th International School on Nuclear Power Hitachi-GE Nuclear Energy, Ltd. Property ABWR Reactor Technology Polish benefits from a U.K deployment Kazue Okumura HGNE Nuclear Engineering David Hinds GEH Nuclear Engineering November 16, 2017 Hitachi-GE Nuclear Energy, Ltd Hitachi-GE Nuclear Energy, Ltd All rights reserved.

2 About us - company profile Hitachi, Ltd. General Electric Company Hitachi equity share: 80.01% GE equity share: 19.99% Hitachi equity share: 40% GE equity share: 60% Hitachi-GE Nuclear Energy (Established on July 1, 2007) GE Hitachi Nuclear Energy (Established on June 4, 2007) Hitachi-GE Strength Full System Design Manufacturing Construction Integrated CAE Advanced Technology Synergy Systems Design GE-Hitachi Strength NSSS Design Global Execution- NPP, Services, Fuel Global Supply Chain Advanced Technology Licensing GE-Hitachi alliance based on nuclear business collaboration for 50 years Committed to develop and promote latest BWR technologies and services 1

3 Hitachi-GE business profile Company Name Hitachi-GE Nuclear Energy, Ltd. Founded July 1, 2007 New Plant Build Maintenance Service 2 ABWRs under construction Outage services for 20 operating units Global Business development Plant modification, Life extension, etc. Shimane 3 Ohma 1 Fuel Cycle Water Jet Peening Monju / Rokkasho Commissioning Interim Storage Casks Monju NPS (Prototype FBR) Rokkasho Reprocessing Plant Shroud Replacement 2

4 Hitachi/Hitachi-GE construction experience More than 20 BWR units continuous construction experience All of our proven and advanced technology is consolidated in ABWR ABWR Other BWRs Tokyo Electric Power CO. Kashiwazaki-Kariwa-6/7 (1996/1997 C/O) Electric Power Development CO. Ohma-1 (Under Construction) (Full MOX ABWR) Chugoku Electric Power CO. Shimane-3 (Under construction) Hokuriku Electric Power CO. Chubu Electric Power CO. Shika-2 (2006 C/O) Hamaoka-5 (2005 C/O) 3

5 ABWR - advanced and proven technology Most experienced Generation III+ reactor in the world advanced, proven and operating Safe, reliable and cost competitive Simplified systems with high operability Short & credible construction Design certified by the US-NRC, 1997 First license approved in 1991; 5 ABWRs in Japan 1350 MWe class World s 1 st & 2 nd ABWRs: Kashiwazaki-Kariwa 6&7 (Operation start : 1996 & 1997) 4

6 ABWR evolution ABWR technology is always evolving Incorporating customer requirements, site conditions and ABWR Evolution Improvements based on plant operating experience and technological advancements Avoid FOAK Risks Kashiwazaki-Kariwa Unit 6 & 7 Hamaoka Unit 5 Shimane Unit 3 * Shika Unit 2 Proven Technology Hamaoka Unit 5 Taiwan Lungmen Unit 1 & 2 * Ohma Unit 1 * *before commercial operation 5

7 Key plant / reactor characteristics ABWR Parameters Core Thermal Power Output MWt Uprate capability MWt Plant Net Electrical Output (1) MWe Reactor Operating Pressure MPa (1040 psia) Feed water Temperature (2) 216 O C (420 O F) RPV Diameter 7.1 meters (24.3 ft) Height 21 meters (68.9 ft) Reactor Recirculation 872 fuel bundles Fuel length meters (12 ft) Average power density. 51 kw/liter Control blades 205 fine motion control rod drives (1) Typical (site dependent) (2) Nominal Rated Operation 6

8 ABWR high level operational flow paths Simplified systems with high operability Efficient performance - direct cycle 7

9 ABWR general features Safe Inherent safety features Large system and structure margins Reactor Building Economical Efficient performance - direct cycle Simple configuration - fewer components & no steam generators Small size high power output High fuel utilization Predictable and efficient construction Reactor Pressure Vessel Primary Containment Vessel Turbine Building Fuel Control Rod Steam Turbine Generator Recirculation Pump RIP: Reactor Internal Pump Water Feed water Pumps Circ. water Pumps Cooling water (Sea water) Water Intake Discharge 8

10 ABWR key technologies Reinforced concrete Containment Vessel (RCCV) 52inch long turbine blade Moisture Separator Re-heater(MSR) Increased Safety Avoidance of large pipe break accident using RIPs 3-division ECCS Improved Operation Precise power control using FMCRDs and RIPs Intelligent Man-machine Interface Reactor Internal Pump (RIP) Improved Economy Improved thermal efficiency using 52 inch or longer turbine blade and MSRs Downsizing building volume Increased Reliability Intelligent Man-machine Interface Fine Motion Control Rod Drive (FMCRD) Dual CR drive system (FMCRD) Digital Instrument and Control System 9

11 ABWR Construction Achievements Construction durations (months) F/C First safety concrete F/L Fuel load Plant F/C F/L Start up Total P *1 A *2 A *2 P *1 A *2 Plant status Kashiwazaki-Kariwa Operation (1996-) Kashiwazaki-Kariwa Operation (1997-) Hamaoka-5 43 *3 43 * Operation (2005-) Shika Operation (2006-) Shimane Under Construction Ohma Under Construction *1: Planned months, *2: Actual months, *3: Including suspended time Well coordinated development phase engineering Advanced construction techniques On schedule and on budget execution Risk mitigation and cost savings for plant owner 10

12 New construction challenges New nuclear construction challenges Historically over schedule and budget Significant delays and rework due to many factors HGNE s approach Comprehensive, detailed, well coordinated, project development phase prior to construction start Integrated engineering, design and construction management processes and tools Project specific detailed design that is well advanced prior to construction Integrated project specific supply chain, logistics and scheduling Project specific IT solution implemented Project development phases are typically several years in duration HGNE s results On time construction Executed within budget Point out 11

13 Achieving On Schedule and On Budget Project Development Phase work product Integrated data management through total plant life (3D plant CAE) Integrated plant construction methodologies and management Advanced site specific design engineering before starting construction less rework 3D design output of reactor area Actual installation work of reactor area Construction and component installation are performed as designed and planned during the Development Phase 12

14 Horizon Project Overview Deploying Hitachi-GE UK ABWRs 5.4GW of new capacity across two sites (Wylfa and Oldbury) c.10 million homes Up to 60% of project value could be spent in UK Employment: around 8,500 people at peak construction Wylfa Newydd Sunrise House (HQ) Oldbury Mr. Duncan Hawthorne has joined Horizon as Chief Executive Officer from May 1,

15 Horizon project schedule GDA *1 Complete FID* 2 COD* 3 (First half of 2020s) Step 1 Step 2 Step 3 Step 4 PAC1 *4 PAC 2 DCO *5 DCO Granted SLA* 6 SLA Granted EPC Consortium established FNC *7 Preparatory Works Construction Near-term milestones Dec. 2017, GDA (safety assessment) complete 5 year process Mid-2018, DCO granted start significant site work Site licensing well underway... supports mid-2020 construction start All on schedule and on budget *1:Generic Design Assessment *2:Final Investment Decision *3:Commercial Operation Date *4:Pre Application Consultation *5:Development Consent Order *6:Site License Application *7: First Nuclear Construction 14

16 UK and Poland project synergies Extensive synergies expected Design common ABWR technology Licensing similar European safety requirements Procurement common supply chain in EU market Manufacturing production efficiencies as volume increases Staffing continuous and secure recruitment Construction deploy well-trained skillful workers; leverage construction training programs Training EU based operator training center Operation leverage ABWR fleet operating experience Maintenance leverage ABWR fleet best practices; potential for common spare parts pool 15

17 Transfer to Poland Safety Analysis Event Categories Design requirements associated with mitigation features depend on event category Event categories have been compared between different regions of the world Poland categories based upon IAEA requirements with country specific aspects ABWR verified to meet requirements in US, UK, and Japan ABWR team is prepared to meet the Polish requirements 17

18 IAEA Requirements - Defense Lines Conservative Design and High Quality Construction and O&M Preventative Line of Defense Main Line of Defense Backup Line of Defense Emergency Preparedness Level 1 Level 2 Level 3 Level 4 Level 5 Public and Environment Postulated Initiating Event Potential Release Potential Transient Progression Potential Transient Progression Potential Transient Progression Frontline Systems Frontline Systems Frontline Systems Support Systems Independence Support Systems IAEA Defense in Depth requirements addressed in Poland ABWR 18

19 ABWR Emergency Core Cooling System IAEA Defense Line 3 Significant operating and licensing experience 18

20 ABWR ECCS very safe and reliable Design principles RCIC system Redundancy duplicate systems PRIMARY CONTAINMENT Diversity different solutions for the same event Common cause failure elimination/ mitigation RPV MAIN STEAM LINE "B" TO FEEDWATER LINE "B" Three physically separate mechanical & electrical divisions for: Core cooling Heat removal Electrical power from emergency diesel generators SUPPRESSION POOL POOL S KEEP FILL PUMP TURBINE MAIN PUMP FROM CONDENSATE STORAGETANK Each division has both high and low pressure injection High Pressure - Reactor Core Isolation Cooling (RCIC); High Pressure Core Flooder (HPCF) Low Pressure - Low Pressure Flooder (LPFL) PRIMARY CONTAINMENT HPCF system RPV SLC (B) Station Blackout (SBO) addressed Steam-driven Reactor Core Isolation Cooling (RCIC) pump Alternate power source Diverse coolant injection FROM CONDENSATE STORAGE TANK MAIN PUMP SP 19

21 Anticipated Polish Requirements - ABWR Anticipated requirements and considerations IAEA based requirements WENRA considerations EUR considerations ABWR EUR compliance review completed in 2001 Largely compliant with EUR guidance Exceptions to EUR have been evaluated US and UK ABWR address aircraft impact requirements Defense lines including the backup (fourth) defense line, which was added more recently addressed in global ABWR projects ABWR team prepared to provide an optimized plant based on Polish requirements and regulations 20

22 ABWR technology ABWR technology Predictable cost and construction schedule Hitachi-GE has the most advanced construction methods in the industry, achieving On-schedule & On-budget results Reliable operation Design refinements from almost 2 decades of operating experience Continuous improvement Feedback from Hitachi-GE maintenance services organization is submitted to the design process to improve manufacturing, modularization, construction and operability Designed for Poland Polish ABWR will need to meet local requirements and regulations as well as be optimized for site specific conditions 21

23 Hitachi-GE Nuclear Energy, Ltd. JAPAN March Hitachi-GE Nuclear Energy, Ltd All rights reserved.