innovations in nuclear reactor designs - international … claims based on the u.s. doe commissioned...

1 Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Innovations in nuclear reactor designs

IAEA Technology Assessment for New Nuclear Power Programmes 1st -3rd September 2015 Vienna

David Powell VP Nuclear Power Plant Sales Europe GE Hitachi Nuclear Energy

Presentation topics: - GE Hitachi Nuclear - Technology Innovations - Market Deployment - Conclusions

GE Hitachi Nuclear


Leading global BWR nuclear provider

Ownership GE 60% GE 60% GE 51% Hitachi 80%

Hitachi 40% Hitachi 26% Hitachi 25% GE 20% Toshiba 14% Cameco 24% Key segments Services, New Units, Fuel Fabrication Uranium Services and New and Canada and Engineering Enrichment Units in Japan

General Electric Hitachi Nuclear Alliance

Company

Copyright 2013 GE Hitachi Nuclear Energy - All rights reserved 5

Two strong global parent companies

General Electric • Operating in >100 countries

• 125+ year legacy • >300,000 employees worldwide • 2013 global revenue €107B

Hitachi • 100+ year history • >360,000 employees worldwide • 2013 global revenue ~ €69B

GE in Europe • Operating here for over 100 years • 90,000+ employees • Annual revenues of ~€18B

(~20% of GE’s global revenue)

Hitachi in Europe

• Operating here since 1982 • ~10,000 consolidated employees • Annual revenues of ~€5.8B

(~7% of Hitachi’s global revenue)

Combined • More than 225 years of company history • More than 660,000 employees globally and 100,000 in Europe • ~€175B in revenue globally and ~€24B in Europe

Copyright 2015 GE Hitachi Nuclear Energy International, LLC – All rights reserved


Unlocking value for customers & shareholders

Enhanced Renewables offerings

Adds ~$10B rev. to GE’s Footprint

$1.2B+ synergies potential

Combined 1,400 GW Installed Base • Broad services business • Big installed base ~350GW

Services Growth

• Steam Turbine Leadership • Integrated Power Package

Power Plant Broader Power Plant Portfolio

• Leading Hydro player • Offshore wind capability

Expand Renewables Platform

• Broad high voltage grid business • More competitive w/market leaders

Grid/T&D Capabilities

• Emerging markets footprint

Synergies • Synergies from global structures

Broader geographies

$7B Grid Business


Vallecitos – USA

Dresden 1 – USA

Laguna Verde - Mexico

Tarapur 1&2 – India

Dodewaard - Netherlands KKM - Switzerland

Garigliano - Italy

Santa María de Garoña - Spain Lungmen - Taiwan

K6/K7 - Japan

KRB - Germany

60 years of BWR development globally

Technology Innovations


GE Hitachi’s reactor portfolio

PRISM ESBWR

Operational Gen III active safety technology

NRC certified design

• Lowest core damage frequency of any Generation III reactor

• Extensive operational experience since 1996

• Licensed in US, Taiwan, Japan • First concrete to first fuel … 39 to

45 months

Evolutionary Gen III+ passive safety technology

NRC certified design

• Lowest core damage frequency of any reactor … safest design

• Passive cooling for >7 days w/o AC power or operator action

• Lowest projected operations, maintenance, and staffing costs1

• 25% fewer pumps, valves and motors than active safety plants

Revolutionary Gen IV sodium cooled technology

Ultimate used fuel solution

• Passive air-cooling w/no operator or mechanical actions needed

• Ultimate answer to the used fuel dilemma - reduce nuclear waste to

~300-year radiotoxicity2 while generating new electricity

• Also solution for Pu disposition

1 Claims based on the U.S. DOE commissioned ‘Study of Construction Technologies and Schedules, O&M Staffing and Cost, and Decommissioning Costs and Funding Requirements for Advanced Reactor Designs’ and an ESBWR staffing study performed by a leading independent firm

2 To reach the same level of radiotoxicity as natural uranium

ABWR


GEH new nuclear plant development

Worldwide BWR fleet K6/K7 – First ABWRs Borax BWR test facility

ESBWR

SEFOR, Fermi I, Seawolf, FFTF

US sodium reactor experience EBR EBR-II PRISM

1950’s 1980’s 2000’s

lessons learned … customer input … new features … testing … studies … detailed design


BWRs are simpler, safer, easier to operate

III+ III+

U.S. PWRs

2 E-5 (avg.)

U.S. BWRs

8 E-6 (avg.)

APR1400

2 E-6

APWR

1.2 E-6

EPR

2.8 E-7

AP1000

2.4 E-7

ABWR

1.6 E-7

ESBWR

1.7 E-8

PR

A o

f C

ore

Da

ma

ge

Fre

qu

en

cy

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

Generation III … III+ Generation II


ESBWR ESBWR

Simplicity reduces equipment and maintenance

Everything in one vessel

Extra components impact: • Manufacturing • Installation • O&M • Decommissioning

•ESBWR doesn’t require: steam generators, pressurizer, reactor coolant pumps, primary loop piping

•PWR heat exchange surfaces (steam generators) wear out over 20-30 years … 1/3 of ESBWR’s heat exchange surfaces (fuel) are replaced every outage (~2 years)


Best-in-class SBO response

Gen II, EPR Water Operator

Action Electric Power

72 HRS.

>7 days

AP1000

ESBWR

*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; VVER AES-2006: Stuk Preliminary Safety Assessment

Responses needed to prevent core damage during extended loss of all AC power

• Gen III+ passive plants allow for a much longer coping time • Decay heat level impacts urgency

DECAY HEAT

ABWR

~36 HRS.*

30 MIN.

24 HRS.

30 MIN.

VVER AES-2006

24 HRS.


Advanced Boiling Water Reactor

ABWR Key Features


The Advanced Boiling Water Reactor

99.9% Steam

550⁰ F / 288⁰ C

420⁰ F / 216⁰ C

BWR Fuel Assembly - 90 fuel rods encased in a ‘channel’ - 2 water rods - Part-length rods - Burnable absorbers

Reactor Pressure Vessel

Steam Dryer

Steam Separator

Control Rod Drives

Control Rod Blades

Reactor Internal Pumps (ABWR)


ABWR station blackout prevention and mitigation

3 x 100% nominal safety divisions

Emergency Diesel Generators • 3 located in Reactor Building

• Each has a 7-day fuel tank that is buried in a concrete vault outside the Reactor Building

Combustion Turbine Generator • Air-cooled – Service Water not

needed

AC Independent Water Addition (ACIWA) System • Hard-piped connections to

reactor


ABWR project experience

Hamaoka-5 COD 2005

Kashiwazaki-Kariwa 6 COD 1996

Kashiwazaki-Kariwa 7 COD 1997

Shika-2 COD 2006

Under Construction

The only Gen III Reactor with operating experience … +25 years

Ohma 1 38% complete

Shimane 3 94% complete

Lungmen 1&2 94% complete

Pre-op testing

Operational

Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy

Constructed on time … 39-45 months


ABWR to ESBWR evolution: Nuclear Island

1

1

1

Fuel and Aux Pool Cooling – equivalent designs 2

Reactor Water Cleanup System – equivalent designs

2 2

3

3

3 Suppression Pool Cooling & Cleanup System – equivalent capability

7 High Pressure Core Flooder – replaced by HP CRD makeup

4 Residual Heat Removal System – equivalent for shutdown cooling

6 4

4

7

5

Standby Liquid Control System – simplified design

5 5

8 Reactor Core Isolation Cooling – replaced by Isolation Condenser

8

8

6 Hydraulic Control Unit – equivalent design

7

6

9 Residual Heat Removal Containment Spray – replaced by PCCS

9

9

Safety Relief Valves – Diversified by Depressurization Valves

Systems are Equivalent or Simplified

10

ABWR ESBWR

10

10


Economic Simplified Boiling Water Reactor

ESBWR Key Features


ESBWR overview


ESBWR significant attributes

Safer • Safest reactor design available … lowest CDF • Passive accident response with no AC power or operator action • Hands-free 72-hour design basis accident response • Passively cools for 7+ days following SBO … >2x better than AP1000

Simpler • 25% fewer safety-related components than active plants … 11 fewer systems than ABWR • Simpler to operate and maintain … fewer plant transients and online surveillances

Smarter • 1520 MWe with 20% fewer staff and lowest projected O&M cost per MWe • No steam generators to replace • Dominion & DTE selected ESBWR … NRC certification Oct 2014

Copyright 2014 GE Hitachi Nuclear Energy International, LLC - All rights reserved 21

Passive safety utilizing the laws of nature: natural circulation and gravity

21


ESBWR passive safety systems No AC power or operator action required!

Isolation Condenser System: Closed-loop

cooling system

transferring reactor decay

heat to atmosphere; activates automatically if DC power is lost

Gravity Driven Cooling System: Passively injects water into the reactor via gravity in case of LOCA

Suppression Pool: Provides heat sink for initial LOCA depressurization

Automatic Depressurization System: Passively

depressurizes the

reactor and keeps it depressurized following a LOCA

BiMAC core catcher: Passively cooled core catcher

Passive Containment Cooling System: Passively transfers decay heat out of containment, sending water to GDCS pools

Standby Liquid Control System: Passively injects borated water into the reactor for backup shutdown capability

x 6 x 4

x 3


ESBWR … ‘Proven’ innovation PCCS heat

exchanger test

IC/PCC POOLS

DW2

GDCS POOL

WW2

WETWELLWW1

RPV

DRYWELLDW1

GIST facility

Isolation Condenser Testing

BDL

BREAK

LOWER

DRYWELL

HORIZONTAL

VENT (1 OF 2)

GDCS INJECTION

LINE (1 OF 4)

UPPER

DRYWELL

VACUUM BREAKER

(GDLB TESTS ONLY)

MSL

BREAK

REACTOR

PRESSURE

VESSEL

DEPRESSURIZATION

LINE (1 OF 2)

WETWELL

Panda Full Height Containment Test facility

WW to DW Vacuum Breaker

drywell to wetwell vacuum breaker test

Depressurization Valve test

BiMAC testing

fuel – modified

GNF2

natural circulation proven at Dodewaard

FMCRDs from ABWR

Copyright 2015 GE Hitachi Nuclear Energy International, LLC – All rights reserved


ESBWR modularization – based on ABWR Roof Truss Steels

RCCV Top Slab

RCCV liner

Central Mat

Base Mat HCU Room Offgas Equipment Lower Condenser Block

T-G Pedestal Piping Unit

Upper Condenser

Condensate Demin. Piping

Condensate Demineralizer Upper Drywell Module

RPV Pedestal

MSIV RWCU Reheat Exchanger


ESBWR reduces dose

0

0.5

1

1.5

2

2.5

3

Co

lle

cti

ve

Do

se (

pe

rso

n-r

em

) p

er

MW

-Ye

ar

BWR PWR

ABWR

ESBWR (projected)

ESBWR dose reduction vs GEN II

• Simplified design/less maintenance

-No recirculation or ECCS pumps/pipes • Cobalt containing material reduced 50+%

• Improved Reactor Water Cleanup • Greater remote maintenance/inspection

Source: U.S. NRC; Hitachi GE

• Shielding minimizes N-16 operating radiation •N-16 is not an issue during maintenance …

decays @ T1/2 7.1 seconds


ESBWR offers substantial O&M improvements

Easier to maintain Simpler to operate

• 25% fewer safety-related components

• 11 systems eliminated – others combined or simplified

• Lowest O&M costs of any Generation III+ technology*

• 50+% more fuel bundles exchanged in same outage time

• Hands-free 72-hour design basis accident response; 7+ day SBO

• Lowest staffing requirements … 20% lower staffing per MWe*

• Fully digital I&C • Fewer plant transients • Fewer online technical

specification surveillances

* Claims based on the U.S. DOE commissioned ‘Study of Construction

Technologies and Schedules, O&M Staffing and Cost, and Decommissioning

Costs and Funding Requirements for Advanced Reactor Designs’ and an ESBWR staffing study performed by a leading independent firm

Passive safety & simplified design


Power Reactor Inherently Safe Module

Key Features

PRISM


Recycling used LWR fuel closes the nuclear fuel cycle with two technologies ...

NFRC - Electrometallurgical separation

PRISM - Advanced Recycling Reactor

Benefits include: • ’Short’-term Waste: ~300 years versus 10,000+*

• Smaller repository • Uranium energy: extracts 90% • Non-proliferation: no plutonium separation • Environmentally responsible: dry process

* Time to reach the same level of radiotoxicity as natural uranium


PRISM overview


Unique design approach of PRISM

PRISM

Active safety systems Passive safety systems Indefinite air cooling

Recirculation loops Pool → No LOCA

Oxide fuel Metal fuel

Large reactors Small → Factory modules

BN-600

Acid chemistry Electrochemistry

2 safety systems to

remove decay heat

Simplified design … cost

savings

Lower stored energy … higher

safety margin

Cost savings and predictable

schedule

Simpler, cleaner, & more cost effective

Market Deployment


ESBWR US NRC Design Certification


Dominion North Anna 3 GE Hitachi ESBWR in U.S.

Dominion selected ESBWR for North Anna 3 Technology attributes … SBO coping Design Certification status Competitive offering

Project Development Agreement (PDA) Site-specific ESBWR design & COLA

licensing support Cost & schedule control incentives Financial risk allocation process Negotiated EPC contract (unsigned)

Fault-based, joint & several consortium GEH – consortium leader … NI design &

equipment Fluor – site leader … TI/BOP design & all

construction

Leveraging ABWR experience … GEH Lungmen & HGNE Japan

North Anna 3* indicative timeline

• 4/2013 – PDA signed

• 12/2013 - Dominion amended COLA

• Est. 12/2015 - COL approval

• Est. 2019 – Full Notice to Proceed, subject to receipt of all necessary regulatory approvals

• Est. 2021 – First concrete

• Est. 2026 – COD

* Dominion has not yet committed to building NA3, but

expects to make a decision once the COL is received.

COLA – Combined Operating License Application

EPC – Engineer, Procure, Construct COD – Commercial Operation Date

SBO – Station Blackout

NI – Nuclear Island TI – Turbine Island

BOP – Balance of Plant


DTE Energy Fermi 3 GE Hitachi ESBWR

• DTE is first ESBWR COL holder

April 30, 2015 – NRC approved Fermi 3 Combined Operating License for ESBWR

• Fermi 3 will be collocated on 1260 acre site with existing Fermi 2, a 1200 MWe GE BWR/4

• Nov 2007 - ESBWR selected after detailed vendor evaluation

• Combined Operating License Application:

Fermi 3 is Reference COLA (R-COLA)

Created process benchmark for COLAs

Only one DCD departure - increased RadWaste Building storage capacity

• Working closely with Dominion … ESBWR Design Centered Working Group (DCWG)

• GEH supporting licensing, training, and site deployment planning

Fermi 3* indicative timeline

9/2008 – Initial COLA submittal

1/2013 – Env. Impact Statement

10/2014 – NRC certifies ESBWR

11/2014 - Final Safety Eval. Report

2/2015 – Mandatory Commission Hearing

4/2015 - COL approved

• TBD – Commercial Operation Date

* DTE has not yet decided when to build … COL prepares

them to meet State’s future energy and environmental needs


Horizon Nuclear Power, Hitachi GE ABWR in UK

Horizon* indicative timeline • Mid-2013 – Commenced GDA process … a

four step approval process

• Mid-2014 – Completed steps 1 & 2 of GDA process

• Mid-2014 – Commenced Step 3 of GDA process

• Jan 2015 – UK Government issued justification approval

• Est. 2019 – Finance close

• Mid-2020s - COD * Horizon has not yet decided when to build

Horizon Nuclear Power, Ltd. 100% owned by Hitachi, Ltd. (Nov. 2012)

• New Wylfa site

Location: Anglesey, Wales

Adjacent to site w/2 Magnox reactors

Two planned ABWR units

• Oldbury site

Location: South Gloucestershine

Adjacent to site w/2 Magnox reactors

Two planned ABWR units

• GE Hitachi supporting Generic Design Assessment (GDA) of the ABWR by Hitachi GE.

• Engagement with UK stakeholders including supply chain progressing.


UK ABWR

Courtesy of Hitachi GE


PRISM development for UK plutonium

•PRISM currently being considered

in the UK for plutonium reuse.

•UK government policy to re-use plutonium and looking for alternative solutions to provide better value.

•PRISM the technology that “ticks

all the boxes”.

•PRISM declared a “credible option” by the NDA and work proceeding.

•Potential to extend PRISM to close the fuel cycle - reduce used nuclear

fuel to ~300-year radiotoxicity1 while generating electricity.

1 To reach the same radiotoxicity

as natural uranium


Leading nuclear innovation for

Vallecitos - 1957

Humboldt Bay

natural circulation Dresden-1

BWR/1 KK6/KK7

ABWR

North Anna-3 ESBWR

PRISM

Oyster Creek

BWR/2 Cofrentes BWR/6

60 years and beyond …


ABWR

PRISM

…. And set to continue in the future

ESBWR

• Exciting times for nuclear now and in the future.

• Industry is well placed to meet future requirements.

• The future is advanced technology based on safety, simplicity and predictability.


ESBWR response to LOCA*

* LOCA: Loss of Coolant Accident

innovations in nuclear reactor designs - international … claims based on the u.s. doe commissioned...

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