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Introduction to GE Hitachi State-of-the-art NPP technology Nuclear Power Asia 2014 Patrick Looney Commercial Leader, Nuclear Plant Projects General Electric Hitachi Nuclear Energy Copyright 2014 GE Hitachi Nuclear Energy - Americas, LLC - All rights 1 reserved GE Hitachi nuclear alliance and businesses Wilmington, NC Tokyo, Japan Wilmington, NC Wilmington, NC Peterborough, ON USA USA Yokosuka, Japan Canada • Nuclear Power Plants: • Uranium • Nuclear Fuel Fabrication ABWR, ESBWR and PRISM Enrichment ….BWR and CANDU • Nuclear Services … Third • CANDU Services • Advanced Programs … Generation • Fuel Engineering and Recycling Technology Support Services Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 2 reserved GE Hitachi’s new reactor portfolio ABWR ESBWR PRISM Revolutionary technology Operational Gen III Evolutionary Gen III+ technology technology with a rich, 40-year heritage • Lowest core damage • Lowest core damage frequency • Passive air-cooling with no operator frequency of any of any Generation III+ reactor or mechanical actions needed Generation III reactor • Passive cooling for >7 days • The answer to the used fuel • Extensive operational without AC power or operator dilemma - can reduce nuclear experience since 1996 action waste to ~300-year radiotoxicity2 • Licensed in US, Taiwan, • Lowest projected operations, while providing new electricity and Japan maintenance, and staffing generation costs1 • 25% fewer pumps, valves, and 1 Claims based on the U.S. DOE commissioned ‘Study of Construction Technologies and Schedules, O&M Staffing and Cost, and Decommissioning motors than active safety Costs and Funding Requirements for Advanced Reactor Designs’ and an ESBWR staffing study performed by a leading independent firm nuclear plants 2 To reach the same level of radiotoxicity as natural uranium Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 3 reserved Simplicity “Simplicity is the ultimate sophistication” - Leonardo da Vinci Dresden 1 KRB Dresden 2 Oyster Creek ABWR ESBWR Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 4 reserved Simplicity improves safety PRA of Core Damage Frequency PRA U.S. PWRs U.S. BWRs APR1400 APWR EPR AP1000 ABWR ESBWR 2 E-5 (avg.) 8 E-6 (avg.) 2 E-6 1.2 E-6 2.8 E-7 2.4 E-7 1.6 E-7 1.7 E-8 III+ III+ Generation II Generation III References: Plant licensing DCDs and publically available information Note: PRA of CDF is represented in at-power internal events (per year) Note: NSSS diagrams are for visualization purposes only Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 5 reserved Simplicity reduces equipment and costs ESBWR Steam Generator Some similarities • Natural circulation • Steam separators and dryers Some differences • PWR heat exchange surfaces (steam generator tubes) wear out over 20-30 years o Replacing steam generators is costly and risky • ESBWR’s exchange is simply refueling o Routine maintenance for both Source: U.S. NRC; Hitachi GE Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 6 reserved Simplicity reduces equipment and costs All in one ESBWR vessel ESBWR Everything else is just extra that impacts: • Manufacturing • Construction/Installation • O&M • Decommissioning Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 7 reserved Simplicity reduces staffing ESBWR requires significantly fewer plant personnel than any other Generation III/III+ design. • A direct reflection of the ESBWR’s simpler design • Lower O&M costs • Reduced burden for human resource development Source: An ESBWR staffing study performed by a leading independent firm Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 8 reserved Simplicity reduces dose • BWR steam does go directly from reactor to turbine • Operating radiation from N-16 (decays @ T1/2 7.1 seconds) is minimized with shielding 3 • N-16 is not an issue during maintenance … Year - minimal protection required 2.5 ESBWR dose reduction 2 rem) per MW - BWR PWR • Simplified design/reduced maintenance ABWR -No recirculation pumps/pipes 1.5 -No ECCS pumps • Reduction of Cobalt containing material 1 ->50% Co-60 reduction vs. Gen II BWR 0.5 Collective Collective Dose (person ESBWR 0 (projected) Source: U.S. NRC; Hitachi GE Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 9 reserved Simplicity leverages success ABWR ESBWR Systems are eliminated, equivalent or simplified • 11 Systems eliminated • 25% fewer safety-related components Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights reserved 10 ESBWR Passive Safety Systems SLCS Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 11 reserved Isolation Condenser System • Fully passive – only requires gravity to function and starts automatically (fails in-service if DC power is lost) • 4 separate systems in reinforced concrete vaults • Limits reactor pressure (no SRV lifts) and temperature and conserves water inventory following containment isolation • Steam (heat) rises from reactor to the condenser pool, condenses, then gravity pulls the cool water down into the reactor passive (closed-loop) decay heat Removes heat removal Core cooling from containment Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 12 reserved ADS, PCCS and GDCS operation Passive systems working in harmony for a LOCA: PCCS Pool & Heat Exchanger 3 1. ADS – reduce pressure • Reactor pressure is reduced by 10 SRVs & 8 DPVs 2. GDCS – connect circuit & fill DPV • Squib actuated valves allows water to flow from 3 GDCS pools to reactor by gravity 1 3. PCCS – circulate & cool • Natural circulation loop hot steam rises from drywell, condensed in PCCS HX, drains to GDCS • 6 PCCS pool steams off, removing heat from containment 2 ADS - Automatic Depressurization System GDCS - Gravity Driven Cooling System PCCS - Passive Containment Cooling System SRV - Safety Relief Valve DPV - Depressurization Valve Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 13 reserved Responses needed to maintain core cooling Responses to extended loss of all AC power EPR and Operator Electric Water GEN II Action Power 30 MIN. 2 HRS. 24 HRS. ABWR 30 MIN. ~36 HRS.* DECAY HEAT AP1000 72 HRS. • Gen III+ passive plants allow for ESBWR a much longer coping time • Decay heat level impacts urgency >7 days *ABWR DCD credits water addition at 8 HRS. References: AP1000: US DCD rev. 18 Section 8.5.2.1, EPR: US DCD Rev. 1 Section 8.4 Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 14 reserved Backup refill options for >7 day cooling OR Only 9kW/12HP pump needed for ICS pool refill OR OR Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 15 reserved ESBWR conclusions Simplification • Less equipment • Lower capital costs • Lowest staffing levels • Less maintenance costs “Simplicity is the • Lower dose ultimate sophistication” - Leonardo da Vinci • Safest (lowest CDF) The most advanced passive technology • Uses the forces of nature • >7 day passive cooling capability Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 16 reserved Thank you Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 17 reserved .
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