UE-BX-0167
The Workshop on Innovative Nuclear Energy Systems

Development of Hitachi-GE's Advanced Reactors
January 26, 2024

Kazuaki Kito
Hitachi-GE Nuclear Energy, Ltd.
© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Hitachi and GE global alliance

Hitachi, Ltd.

General Electric Company

Hitachi-GE Nuclear Energy

GE Hitachi Nuclear Energy(Established on July 1, 2007)

Synergy

Hitachi-GE Strength
Full System Design
Manufacturing
Construction
Integrated CAE
Advance Technology••(Established on June 4, 2007)

GE Hitachi StrengthSystemsDesign

NSSS Design
Global Execution-NPP,Services, Fuel
Global Supply Chain
Advance Technology
Licensing

Hitachi and GE alliance based on nuclear business collaboration for 50 years
Committed to develop and promote latest BWR technologies and services© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Hitachi-GE nuclear business scope
Spent fuelcask

Rokkasho
Reprocessing Plant

Components supplyfor Monju (SFR)
or Rokkasho
Spent fuel Interim
Storage Casks

Fuel Cycle

HI-ABWR

BWRX-300 (SMR)

New Builds
Multiple ABWRs in operationand under construction
Promotion to global market

Maintenance ServicesRobotics for Fukushima

Safety enhancement of Japanese NPPs toallow restart
Fukushima Decommissioning etc.
Operating plant maintenance service

Filtered Containment Vent

© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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3World Trend on Nuclear Power

Recent New Builds

Future New Builds

Decom Units Increasing

Utilizing existing units• ~60% of newbuilds constructedby China or Russia• Russia holds large
portion of replacemarket• Majority of planned
units to be constructed by China orRussia• Small number ofplants planned in US,
UK and Canada• Government policy
or economic reason
to shutdown oldunits• Utilizing existing units
are on-going in manycountries• Improvement on
availability and 60/80
years operation being
promoted in US

CarbonNeutral• Based on the Paris agreement,
more than 150 countries/regions
had declared CN in 2050
• Plan for large scale deploymentof renewable energy• US launched and promoting advanced
reactors by ARDP (Advanced Reactor
Adv. Reactor
Demonstration Program)
Development• Canada declared nation’s Action Plan
to promote SMRs in Canada

Prepare for changes of environment in nuclear power© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Trend on Advanced Reactors Deployment
US Canada: SMR demo/construction, UK/France: Both large and SMR

CountryUSARecent
Promote SMRsCanada

UK Support for large scale
reactor project, while
SMR development isunder consideration
FranceSMREU Preparing
development
TVA： Tennessee Valley Authority

Current Status• TVA announced to proceed with BWRX-300• DOE chose small fast reactor and high temperature gas
reactor in ARDP (Adv. Reactor Development Program)• OPG and SaskPower picked BWRX-300 for deployment• Declared to be a leader in SMR technologies• UK Gov supports Sizewell C project (2 EPRs), with aiming tobuild max. 8 reactors and to realize 25% by nuclear (2050)• Great British Nuclear has been launched by government witha mission to identify the best small modular reactor (SMR)
technology for the UK (potentially 2 units)• FNEF(Future Nuclear Enabling Fund) for SMR developments• President supports 6 units of EPR2 (potentially 8 units)• Promoting to develop/deploy SMRs
• SMRs deployment planned in Poland, Estonia and Czech tofollow• Cooperating in regulatory issues for deploying SMR

OPG： Ontario Power Generation© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Hitachi-GE’s Nuclear Future Vision in Japan

Creation of new value and contribution to safe and sustainable power generation
Value

2020

2050

2060

• Global standard design
based on Fukushima L&Land UK GDA• Installing new safetymechanisms

ABWR- Utilize Pu as resource- Reduction of spent
fuel toxicity

2040

Large reactor with improved safety
to secure stable power supply

Stable energy
sourcecontributing tocarbon neutrality

Improved energy
self-sufficiency

2030*(SMR) - Needs of small to medium power supply- Replacement of old plant

Sodium-cooled
fast reactor(PRISM)

Burnup of Pu by lightwater reactor MOX fuelGradual utilization of fast neutron:- Efficient burnup of Pu, Pu multi-recycling,
Reduction of rad waste toxicity and volume

Light water-cooled
fast reactor (RBWR)

RBWR: Resource reusable BWR, PRISM: Power Reactor Innovative Module* BWRX-300 has been being developed with our sister company GE Hitachi Nuclear Energy.

© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

56Concept of Highly Innovative ABWR (HI-ABWR)

Based on international standard ABWR※ which considers Fukushima lessen learned and meet
UK/European requirements, further new safety mechanisms are implemented※：UK Design AcceptanceHighly Innovative ABWR (HI-ABWR)
Confirmation (DAC) granted

Reactor to be accepted by society that experienced Fukushima
1. Innovative safety
 Stronger measures for natural disaster,
terrorism, internal hazards

2. Contribution to carbon neutral BWR’s inherent flexible operation for social needs 10x10 fuel for high burn-up, uprate, extended cycle, full core MOX
 Load following Strengthen building for airplane crash Enhanced seismic design
Built-in Fukushima lesson learned Safety-divisional separation
barrier for internal hazards
APC-resilient Building Passive safety system
 PRCS*1
 Core cacher ＋ LDF*2
 COPS*3

 Cut externalities during
severe accident

 Compact radioactive (noblegas) filter

PRCS (passive)
Separation barrierCore catcher＋LDF (passive)
Noble gas filter(remove from released gas) Competitiveness amongdiverse power sources Innovative but maturedsystems, proven ABWR
construction method

 Operation/maintenanceefficiency
 Next generation controlroom
 Designed formaintenance*1：Passive Reactor Cooling System*2：Lower Drywell Flooder*3：Containment Over pressure
Protection System© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Safety systems of HI-ABWR (1/2)
Airplane crash countermeasures

Containment system for radioactive materials

Protection planned according to NEI
guideline (NEI 07-03), reviewed in UK ABWR
licensing.

Noble gas filter avoids to release radioactive
noble gases while releasing steam andhydrogen during severe accidents.

•••

Physical damage: protection by exterior walls
Fire: safety-divisional separation barriers protect sothat at least one safety division always survives
Shock vibration: the effect is reduced by exteriorwalls

DBA sys.
div. A

Example of physicaldamage analysis

Reduce the risk of hydrogen combustion
Reduce the risk of local resident’s evacuation

Containment
vesselSteam,hydrogenN2,noble gas

Noble gas filter

SA sys.

Containment
vessel
DBA sys.
div. B••

DBA sys.
div. C

Safety-divisional
separation barrier

Organiciodine
filter（イジ）XeFilter unit

Steam,hydrogen,N2, FPKr
H2

Filter vent system(remove FP)

H2O© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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Safety systems of HI-ABWR (2/2)

PRCS: Passive Reactor Cooling System••

Decay heat can be removed by natural circulation
during severe accidents.
No operator actions are required for 24 hours
with automatic start.

Densitydifference
enablesnaturalcirculation

Condensedwater

Steam from RPV
is condensed bywater in PRCStankLDF: Lower Drywell Flooder••

Core catcher prevents the concrete erosion bymolten debris.
Cooling water is supplied from suppression pool
(S/P, enough for 3 days cooling) without operator
actions using fusible plug valve which is open
automatically when the atmosphere heatups.
Reactor pressure vessel

PRCS tankContainment vessel

Steam

FDW系
HPCF系

Reactor pressurevessel (RPV)

Active debris
cooling system

Lower drywell
Molten debris

Injection of S/P water
Fusible plug valve
Thermal-resistantmaterialConcreteCore catcher© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

89Major Features of BWRX-300
Small LWR with enhanced safety, economy, construction and flexibility
Developing with our sister company, GE Hitachi Nuclear Energy
Innovative safety system

Mitigating
LOCA

Integral RPV
Isolation Valve

Cost Reduction
Introduction of innovative system
leads to reduction of SSCs*

7 days cooling without
power/actions

Cooling Pool

ABWR

Isolation Condenser
System (ICS)BWRX-300* SSCs: Structures, Systems and Components

Shortened construction

FlexibilityOperation

Module construction technology

Example of dailyload change

Module of HP
Drain Pump/Piping/Valvesfor ABWR

6121824Siting
EPZ**:
10 mileradiusTarget:site boundary

Mitigated effects ofResponding to daily
severe accident leads toload change
small EPZ**** EPZ: Emergency Planning Zone

© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

910 Innovative Safety System

Natural circulation design +Isolation Condenser System (ICS) +Integral Isolation Strategy
Outcomes:

Integral RPV Isolation Valve• LOCA (Loss of Coolant Accident)
mitigation• Eliminates need for multiple systems• Removes decay heat while maintaining
water inventory• Inherently safe with no operator action
or AC power• 7 days cooling without power/actions
Isolation Condenser System© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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11 Integral RPV Isolation Valve
Breakthrough innovation concept to mitigate large and medium LOCA
• Large non-isolable pipes
between RPV and isolation
valves eliminated• Large break Loss of Coolant
Accident (LOCA) potential
greatly reduced• Nuclear Regulatory
Commission (NRC)
approved in the U.S.
• Enables dramatic designsimplification and eliminationof unnecessary systems© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

1112 Countermeasures for Natural Disasters and Terrorisms
Cylindrical building with sloped roof
• Tornado and typhoon• Airplane crash

Ground level

Containment mostly underground• Airplane crash• Earthquake• Other terrorisms

Other countermeasures
 FLEX (mobile equipment) Safety-divisional separation barrier
 Equipment for severe accidents© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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13 Example of Hitachi-GE activity: BWRX-300 chimney
To support global licensing, CFD and test to validate chimney flow characteristics(water and steam fluxes ⇒ Void fraction ⇒ Density)
Steamseparators

Steam + water loops

Chimney

15mHighdensity
Downcomer

Low density
Test body(0.5m I.D.)

Core

1
0.9

Natural circulation

Benchmarking
system code TRACG

Wire-meshsensor

0.8

Void fraction αm [-]RPV

HUSTLE facility

0.7
0.6
0.5
0.4
0.3
0.2
0.1
0-300

Steam flow rate：
HML-200-100

0100

200300Obtained validation data
© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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14 Deployments of BWRX-300
In Canada, OPG(Ontario Power Generation) progressing to deploy BWRX-300
Important licensing documents approved in USA
Europe- Poland: ORLEN Synthos Green Energy(SGE)partnered to deploy multiple BWRX-300s- Polish regulator: General Opinion and Decision inPrinciple for 6 sites with multiple BWRX-300s each
- Estonia: Fermi Energia choses BWRX-300- UK: GE Hitachi applied for GDA
UKEstonia
PolandHitachi-GE

Hitachi-GE- Developing BWRX-300 from the beginning- Try to establish Supply Chain for domestic
and supporting global projects
DNNP: Darlington New Nuclear Project
GDA: Generic Design Assessment
GEH: GE Hitachi Nuclear Energy
GNF-A: Global Nuclear Fuel - Americas
OPG Ontario Power Generation
TVA: Tennessee Valley Authority
VDR: Vendor Design Review

Canada・ OPG DNNP – first unit deployment status- License to Construct application submitted- Site preparation started- Initial contract for EPC signed
・ Licensing activities on-going- VDR completed- License to Construct under review
・ Next BWRX-300s (3 in Darlington, SaskPower)

USA

TVA Clinch River

OPG Darlington
GEH,GNF-A

Utilities actions- Tennessee Valley Authority (TVA)
progressing with deploying the BWRX-300 atits Clinch River site
Licensing activities on-going- 5 Licensing Topical Reports (LTRs) issued
and approved© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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15 Summary
 Nuclear power is an important source of low-carbon electricity.
 Hitachi-GE is developing four advanced reactors to contribute carbon
neutrality with stable and self-sufficient energy source.
 In this presentation, I introduced innovative large LWR HI-ABWR and highly
economic small LWR BWRX-300. Both reactors have innovative safety
features and countermeasures for natural disasters.
 Hitachi-GE will propose innovative technologies by open innovation with
global collaboration schemes. It contains the cooperation with thegovernments, academia and industries.

© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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END
Development of Hitachi-GE's Advanced Reactors
January 26, 2024

Kazuaki Kito
Hitachi-GE Nuclear Energy, Ltd.

© Hitachi-GE Nuclear Energy, Ltd. 2024. All rights reserved.

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