Advanced
Boiling
Water
ReactorThe ﬁrst Generation Ⅲ+ Reactor in Operation today

Energy production technologies forsustainable future
Advanced Boiling Water Reactor - The first Generation Ⅲ+ Reactor in Operation today with Enhanced Safety, Performance and Cost Efficiency.

Shimane 3 , The Chugoku Electric Power Co., Inc.
1

- Nuclear Energy Nuclear Plant Technologies
Boiling Water Reactor History and Line-UP ・・・・・・・・・・・・・・・・・ 3
Advanced Boiling Water Reactor ・・・・・・・・・・・・・・・・・・・・・・・・・ 5
ABWR Countermeasures Against Fukushima Accident ・・・・・・・ 9

ABWR Structure, System and Component
Reinforced Concrete Containment Vessel (RCCV) ・・・・・・・・・・・ 13
Reactor Internal Pump (RIP) ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 15
Reactor Pressure Vessel (RPV) ・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 17
Reactor Internals ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 19
Control Rods, Control Rod Drives ・・・・・・・・・・・・・・・・・・・・・・・・・ 21
Nuclear Fuel ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 23
Turbine and Generator ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 25
Advanced NUCAMM-90
ABWR Instrumentation & Control Systems ・・・・・・・・・・・・・・・・・ 27
Radioactive Waste Processing Systems ・・・・・・・・・・・・・・・・・・・・ 29
Automatic Equipment ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 31

Project Management Organizations
Organization for Hitachi's Nuclear Business ・・・・・・・・・・・・・・・ 33
Engineering Technologies ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 35
Construction ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 37
Quality Assurance System ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 39
Preventive Maintenance ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 41

Research and Development
Research and Development ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 43

Achievements
Hitachi's Achievements in Nuclear Power・・・・・・・・・・・・・・・・・・・ 45

2

Nuclear Plant Technologies

Boiling Water Reactor History and Line-UP
Simple & Reliable Nuclear-Power Generation System
One of the world's most common types of nuclear power generating plants, boiling water
reactors, are characterized by a system wherein steam generated inside the reactor is directly
passed to the turbine to simplify the process and equipment.
Since the introduction of the boiling water reactor technology, from General Electric in the
1960s, Hitachi has participated in the design, development and construction of over 20 nuclear
power plants within Japan.

The Chugoku Electric Power Co., Inc. Shimane 1

Tokyo Electric Power Company Holdings, Inc. Kashiwazaki-Kariwa 5【 Source：Tokyo Electric Power Company Holdings, Inc. 】

Introduction of Technology from US in 1960s
Tsuruga 1 (The Japan Atomic Power Co.)
Fukushima Ⅰ-1 (Tokyo Electric Power Company Holdings, Inc.)
Hamaoka 1 (Chubu Electric Power Co., Inc.)
Fukushima Ⅰ-4 (Tokyo Electric Power Company Holdings, Inc.)
Tokai Ⅱ (The Japan Atomic Power Co.)
Hamaoka 2 (Chubu Electric Power Co., Inc.)
Promotion of Domestic Plant
Shimane 1 (The Chugoku Electric Power Co., Inc.)

BWR-2

BWR-3,4,5

Primary Improvement
Promotion of Improvement and Standardization Program (1975 to 1977)
Fukushima Ⅱ-2 (Tokyo Electric Power Company Holdings, Inc.)
Fukushima Ⅱ-4 (Tokyo Electric Power Company Holdings, Inc.)
Hamaoka 3 (Chubu Electric Power Co., Inc.)
Shimane 2 (The Chugoku Electric Power Co., Inc.)
Kashiwazaki-Kariwa 5 (Tokyo Electric Power Company Holdings, Inc.)

BWR-5

Improved Version
Promotion of Secondary Improvement and Standardization
Program (1979 to 1980)
Shika 1 (Hokuriku Electric Power Co., Inc.)
Hamaoka 4 (Chubu Electric Power Co., Inc.)
Kashiwazaki-Kariwa 4 (Tokyo Electric Power Company Holdings, Inc.)
Onagawa 3 (Tohoku Electric Power Co., Inc.)

3

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

ABWR Development concept
Safety• Enhanced
Operability• Higher
Dose Equivalent• Reduced• Enhanced Cost Efficiency (Construction/Operation)

The Chugoku Electric Power Co., Inc. Shimane 3

UK-ABWR

ABWR

Application of Evolutional Design and Standardization
The first and second ABWR in the world (Twin plant)
Succeeding ABWR plants
Kashiwazaki-Kariwa 6 (Tokyo Electric Power Company Holdings, Inc.) Hamaoka 5 (Chubu Electric Power Co., Inc.)
Kashiwazaki-Kariwa 7 (Tokyo Electric Power Company Holdings, Inc.) Shika 2(Hokuriku Electric Power Co., Inc.)
Shimane 3 (The Chugoku Electric Power Co., Inc.)
Ohma (Electric Power Development Co., Ltd.)
Higashidori 1(Tokyo Electric Power Company Holdings, Inc.)
Completed Generic Design Assessment(GDA) for
UK-ABWR in December 2017.

4

Nuclear Plant Technologies

Advanced Boiling Water Reactor
ABWR Plant Realized through International Joint Development
Hitachi developed the ABWR in 1985, in collaboration with various international partners andsupport from power companies with experience in operating BWR plants. The maintechnological features employed are as follows:(1) Large scale, highly efficient plant(2) Highly economical reactor core(3) Reactor coolant recirculation system driven by internal pumps(4) Advanced control rod drive mechanism(5) Overall digital control and instrumentation(6) Reinforced concrete containment vessel
These features constitute a highly functional, enhanced safety nuclear reactor systems, with acompact, easy-to-operate, and efficient turbine that offers excellent performance.
■Schematic Diagram of Advanced Boiling Water Reactor (ABWR)
Standby Liquid
Control System (SLC)

Reactor Pressure
VesselDry Well Spray

Reinforced ConcreteContainment Vessel

Main Steam Piping
〜
〜

〜
〜

Low Pressure
Flooder System

〜〜
〜〜
〜〜
〜〜

HydraulicControl
Unit

Suppression
Chamber Spray
〜
〜

〜
〜

Residual Heat
RemovalSystem〜〜〜〜Fine Motion
Control Rod
Drive
SystemControl Rod
Drive Pump
〜
〜

〜
〜

Reactor Core
Isolation Cooling
SystemInternal Pump〜〜

High PressureCore Flooder
SystemSuppression Chamber(Suppression Pool)〜〜

Horizontal Vent
Reactor Water
Clean-Up System

5

Feed Water
Piping〜〜Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Key Specifications of BWR Nuclear Power Plants
Item
OutputReactor
Core

ABWR

BWR-5

Plant Output

1,350 MWe

1,100 MWe

Reactor Thermal Output

3,926 MWt

3,293 MWt

Fuel Assemblies
Control Rods

872

764

205 rods

185 rods

Recirculation System
ReactorEquipment Control Rod Drive

Internal pump method

External recirculation typeHydraulic / electric motor drive methods

Hydraulic drive

Reactor Containment Vessel

Reinforced concrete with built-in liner

Free-standing vessel

3 systems

2 systems

Two-stage reheat

Non-reheat

RHR＊ System
Thermal Cycle
TurbineSystems

Turbine (final blade length)

52 inches

43 inches

Moisture Separation Method

Reheat typeNon-reheat typeHeater Drain

Drain up typeCascade type＊Residual Heat Removal System

Moisture Separator
and Reheater

52" Last Stage Blade
Low-Pressure TurbineHigh Pressure Turbine

Generator

〜
〜

〜〜
〜〜

〜
〜

〜
〜

〜〜
〜〜

Main
Condenser

BypassSystemCooling water
To Off Gas System
Air Ejector
Low Pressure
Condensate Pump

High Pressure Feed
Water Heater

High
Pressure
Drain
Pump

Low Pressure Feed
Water Heater
Gland
Condensate Condenser
Demineralizer
Condensate
High Pressure
FilterCondensate Pump

Low Pressure
Drain Pump
Feed Water Pump
Condensate
Storage Tank

6

Nuclear Plant Technologies

Advanced Boiling Water Reactor
Application of "Evolutional Designs"
・Large capacity, high efficiency plant systems
・Emergency Core Coooling Systems with enhanced safety
・Highly economical reactor core・Reactor recirculation system applying internal pumps
・Advanced Fine Motion Control Rod Drive System
・Advanced Main Control Room with Full Digital system and improved Human- Machine Interface& Automatic Operation
・Reinforced Concrete Containment Vessel■ABWR Reactor Building section view

Reinforced Concrete Containment Vessel
Reactor Pressure Vessel
Steam Dryer
Steam Separator
High Pressure Core Flooder Sparger
Fuel Assembly

7

Control Rod
Reactor Internal Pump
Fine Motion Control Rod Drive System
Control Rod Drive Mechanism Handling Machine
Main Steam PipingOur highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Hitachi's continuous involvement in construction of ABWR power plants(C/O:Commercial Operation)
1st, 2nd ABWRs

Kashiwazaki-Kariwa 6&7(C/O:1996,1997)

5th ABWR Shimane 3 (Under Construction)【 Source：Tokyo Electric Power Company Holdings, Inc. 】

3rd ABWR

Hamaoka 5(C/O:2005)

6th ABWR

Ohma 1 (Under Construction)

4th ABWR

Shika 2(C/O:2006)

7th ABWR

Higashidori 1 (Under Construction)

Reference: http://www.tepco.co.jp/nu/hd-np/plan/plan-j.html
8Nuclear Plant Technologies

ABWR Countermeasures Against Fukushima Accident
Enhanced Safety Features regarding Fukushima-daiichi NPP※ accident
ABWR safety are based on the Defense in Depth (DiD) concept wherein multiple layers ofprotection are provided with each layer designed to provide the safety function with no relianceon the other layers.
ABWR design is compliant with the international criteria by well-designed Safety Systems toachieve a sufficiently low core damage frequency.
Furthermore, to accomplish an enhanced level of nuclear safety, supplementary safetyenhancements against severe conditions have been incorporated. These enhancements onfurther layer in DiD are designed to address the Fukushima-daiichi NPP accident caused by thehuge earthquake and subsequent tsunamis on March 11, 2011.
The major enhancements are the further prevention of Station Black Out (SBO) and/or Loss of
Ultimate Heat Sink (LUHS). Moreover, the enhanced functions ensure water supply into thereactor, PCV integrity, and SFP water level is maintained even in the event of SBO and/or
LUHS.
These enhancements, based on lessons learned from Fukushima Accident, provision andmaintenance of Severe Accident Management Guidelines, ensure that the integrity of inherent
safety features of the ABWR is retained even in the event of a severe accident.
※NPP : Nuclear Power Plant● Diversified water injection methods

ABWR
Safety● Large capacity of heat sink (pool)● Inactivated PCV● High seismic resistance● No large bore pipes lower than the top of fuel assemblies

Core Damage Frequency (CDF):1.6 ×10-7(1) Secure Power Source
・Alternative DC Power Source
・Diversity of Power Source (Water-cooled DG, Air-cooled DG)
・Sealed building structure to secure components and power panels in case of flooding(2) Secure water injection systems and ultimate heat sink
・Diversity of alternate water injection capabilities
・Enhancement of mobility by applying portable pumps
・Diversity of heat sink through use of portable heat removal system(3) Prevention of PCV damage
・Prevention of PCV damage caused by elevated temperatures by enhancing the PCV cooling system(4) Secure Spent Fuel Pool Cooling function
・Diversity of pool water injection method
・Accident Management operability enhancement by applying external water injection filler
・Incorporation of additional SFP temperature and water level monitoring systems in case of severe accident
9Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Inherent
Safety Featuresof the ABWR
Enhancements
Provision andbased on
Maintenance oflessons learned fromSevere Accident
Fukushima Accident Management Guidelines■Overview of Enhanced Safety Systems for Severe Accident
Enhanced PCV
Venting System(COPS)

Stack

Alternative PCVSpray/SFP Coolant
Injection System

Reactor Building (R/B)
PCV Reactor
Well
D/W spray
LPFL×3

Fire fighter
truck

Main Steam line
To turbine
From condenser

W/W
spray

FP-P

Filtered
Vent

Backup Building(B/B)
Alternative AC
Power Source

Filtered water
Storage tank

FLS-P
FMCRD

MUWC-P

CSP

SGTS

SFP

HPCF×2

RCIC×1

RHR×3 Suppression pool

DG or GTG

PCV: Primary Containment Vessel
SFP: Spent Fuel Pool
FP: Fire Protection System
MUWC: Make Up Water System (Condensate)
CSP: Condensate Storage Pool
D/W: Dry Well
W/W: Wet Well

PCVPower truck

COPS: Containment Overpressure Protection System
LPFL: Low Pressure Core Flooder System
HPCF: High Pressure Core Flooder System
RHR: Residual Heat Removal System
RCIC: Reactor Core Isolation Cooling System
SGTS: Standby Gas Treatment System
FLS: Flooder System

10

Nuclear Plant Technologies

ABWR Countermeasures Against Fukushima Accident
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12ABWR Structure, System and Component

Reinforced Concrete Containment Vessel (RCCV)ABWR has increased its power output while also decreasing its containmentsize
RCCV consists of a steel liner inside of a reinforced concrete structure. The RCCV has twofunctions: contain pressure and prevent leakage.
The concrete handles the functions of pressure containment and shielding, and the liner handles
the function of leakage prevention.
The RCCV is divided into a drywell and a suppression chamber by the diaphragm floor and theRPV※1 pedestal.
The suppression chamber contains a pool and an air space. Vapor flows, which are generated
from a LOCA flow from the drywell space to the suppression pool through horizontal vent pipes
embedded into the RPV pedestal.
The design pressure of RCCV is 310kPa. The RCCV design temperature is 171℃ for the
drywell and 104℃ for the suppression chamber.
The RCCV is cylindrical and consists of a top slab, a shell and a foundation. The inside diameterof the RCCV is 29m, and the height from upper surface of the foundation to upper surface of the
top head is 36m.
The thickness of the RCCV shell is 2m and attached to the foundation.
・ Reinforced Concrete Containment Vessel (RCCV) contains reactor pressure vessel.
・ RCCV has reduced its volume and height to improve seismic resistancy.
・ The RCCV compact structure and reactor building integration improves cost effectiveness.
・ In case of RCCV pressure increase, steam is condensed in the Suppression Pool water and a nitrogen
atmosphere can be developed in the PCV※2 to prevent a hydrogen explosion.
※1 RPV : Reactor Pressure Vessel , ※2 PCV : Primary Containment Vessel

More cost-effective

MARKⅠ

MARKⅡ

(BWR-3/4)(BWR-5)

70m

61m

13

55m

52m

Output power : 780MWe

Output power : 1,100MWeOur highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Shimane 3 RCCV Liner module lnstallation

RCCV(ABWR)RCCV : Reinforced
Concrete
Containment
VesselRPV

Drywell

58m

Suppression Chamber

Diaphram Floor
RPV Pedestal

Vent Pipe
57m

Output power : 1,350MWe (ABWR)

14

ABWR Structure, System and Component

Reactor Internal Pump (RIP)
Reactor Internal Pump—High Reliability, High Performance• The Reactor Internal Pump is directly mounted to the bottom of the nuclear reactor pressure
vessel (as shown in figure below) and supplies coolant (water) to the reactor core.
• By controlling Reactor Internal Pump’s rotational speed, the reactor core flow and void
coefficient are changed, thus controlling the nuclear power plant’s power output.
• In comparison to BWR’s with external pumps, motor driving power and radiation exposures
can be reduced due to the elimination of external recirculation pipes.

Reactor Pressure
Vessel (RPV)RIP Casing
RIP

Impeller and Shaft

Impeller and Diffuser

Tilting Pad Radial Bearing

Rotor

StatorStretch tube

Thrust Disk and Auxiliary Cover
15

Motor CoverOur highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Hitachi Reactor Internal Pump Features

Wearing

Technical Data

Reactor Pressure
VesselImpeller and
Shaft

DiffuserNozzleNumber of Pumps

10

Capacity

Approx. 8,300 m3/h*

Total HeadApprox. 46 m*

Speed

Approx. 1,600 min-1*

Design Temp.

302 ℃

Design Pressure

8.62 MPa*Maximum at 120% core flow
Nozzle Gap

Welding

Inspection
Window

Rotor
Wet Motor
Stator
Tilting Pad
Radial Bearing

Thrust Disk
Motor CoverHigh Reliability:• Adoption of Tilting Pad Bearing helps
vibration stability.
• Thicker nozzle yields high earthquake
resistance. (Actual results from past
nuclear power plants.)• The nozzle gap and the inspection
window enable inspection of thewelded area.
• There is a testing facility to test theReactor Internal Pump under the same
conditions in an actual nuclear power
plant.
• In order to eliminate the shaft seal, thewet motor was adopted to connect thepump and motor using one shaft.
High Performance:• 100% core flow is maintained even with
only 9 pumps working.
• High voltage motor is used tocorrespond to the high capacity needs.

Auxiliary Cover
16

ABWR Structure, System and Component

Reactor Pressure Vessel (RPV)
Reactor Pressure Vessel Contains the Core of the Nuclear Power Plant
The reactor pressure vessel contains fuel assemblies, control rods, steam dryer, steam
separator, and other components. With a large separation between the reactor and pressure
vessel walls, BWRs feature low neutron irradiation embrittlement. Hitachi uses highly reliable
vessel materials that further reduce irradiation embrittlement, by reducing the content of copper,
sulfur, and phosphorous in these materials. Additionally, the single-block forging of bottom headand other components greatly reduces weld-line length to be covered by in-service inspections.

Head vent &spray nozzle
Main steam
outlet nozzle(with flow limiter)

Low pressure
flooder nozzle
Low pressure
flooder sparger
High-pressure
core flooder nozzle
High-pressure
core flooder sparger
Top guide
Fuel assemblyInternal pumpControl rod drive
mechanism housing

Reactor Pressure Vessel of Shika Power Station
Unit No. 2 Being Lifted into Building

17

Reactor pressure vessel schematic view

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

RPV Under Fabrication

RPV off loaded at construction site

FlangesSteam dryer
Steam separator
Feed water inlet
nozzleFeed water sparger
Core shroud
Control rods
Core plate
Reactor pressure
vessel support
skirt

In-core monitor
housing

Section view of ABWR reactor building

18

ABWR Structure, System and Component

Reactor Internals
Key Components made by high accuracy manufacturing techniques
Hitachi has designed and manufactured a large number of reactor pressure vessels (RPV) andreactor internal components. Stringent quality control standards guarantee the highest reliability
possible. The expertise acquired to date in design, manufacturing and quality control ensuresthat the reliability of the RPVs and reactor internal components for ABWR facilities will continue
to be every bit as in the past.
■Design & Manufacturing
From small precisely machined components to large welded components, a wide variety of nuclear
core equipment has been designed and manufactured by Hitachi.

Head vent &spray nozzle
Main steam
outlet nozzle(with flow limiter)

FlangesSteam dryer
Steam Separator

Steam separator
Low pressure
flooder nozzle
Low pressure
flooder sparger

Feed water
sparger

High-pressure
core flooder nozzle

Core shroud

High-pressure
core flooder sparger
Top guideTop Guide

Feed water inlet
nozzleControl rods
Core plate
Reactor pressure
vessel support
skirt

Fuel assemblyInternal pumpIn-core monitor
housing

Control rod drive
mechanism housing

Shroud19

Structural sketch of reactor pressure vessel and reactor internal components

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Reactor Internal Components of ABWR

The ABWR reactor internal components are based on the design of the BWR-5 components
which are the evolutionary improvement over the BWR-5 reactor internal components. A numberof improvements were made to enhance the structural strength and higher performance. In
particular, a square hole machining device utilizing extra-high precision technology was used on
the grid plate to manufacture the component from one piece, ensuring outstanding structural
strength.
Structural Comparison of BWR-5 and ABWR
No.

Changes• Steam separator changed from twostage to low pressure-loss three stage
type (AS-2B)

BWR-5

ABWR

Steam Separator（Two stage type）

Steam Separator（Three stage, AS-2B type）

Shroud Head Bolt
Shroud Head1

• Adoption of internal pumps eliminates
large-diameter pipe breaks in bottom ofreactor. This enables core to beconstantly covered in water, allowing
cooling system to be changed fromspray to simple sparger type.

High Pressure Core
Flooder Sparger

Shroud HeadCore SprayTop GuideTop Guide
RPV

RPV
Grid Plate

2

Top Guide• Top guide structure was changed fromassembly of individual matching plates
to one-piece high-structural-strength
one-piece machined type.

Grid Plate

Assembled Grid Plate Type

3

Core Shroud• Inner diameter of core shroud has been
increased to accommodate a larger
number of fuel assemblies.
• Top guide and upper shroud are now
integral.

4

Core Plate• A structure with reinforcing beams andperpendicular reinforcing rods waschanged to all reinforcing beams toincrease strength.

Upper Shroud

Top Guide

Middle Shroud

5

Shell
（Combined with
Guide Plate）

Bolt

Guide Plate

Upper Shroud
Lower Shroud

Lower Shroud

Core Plate

Core Plate

Reinforcing Beam

Reinforcing Rod

RPV
Lower Pressure Flooder System• Adoption of internal pumps eliminates
large diameter pipe breaks in bottom ofreactor, ensuring a constant core
coverage under water. This eliminates
the necessity of supplying water to theinside of the shroud, allowing coolingsystem to be changed to sparger type ofoutside of shroud.

One-piece Grid Plate

ClampsReinforcing Beam（Perpendicular）

Low Pressure Coolant
Injection Pipe
Top Guide

Low Pressure
Flooder Sparger

Top Guide

Bellows
Shroud6

Reactor Recirculation System

Jet Pump

ShroudInternal Pump

20

ABWR Structure, System and Component

Control Rods, Control Rod Drives
Contributing to reduction of plant start-up time, and low radiation exposure
during maintenance• Fine Motion Control Rod Drive (FMCRD) system utilizes two different power sources:-Electric motor drive for normal operation-Conventional hydraulic accumulator for emergency insertion (scram)• Diversification of the power source enhances reliability.
• One way water purge system minimizes the contamination of FMCRD and Hydraulic Control
Unit (HCU) and reduces radiation dose during maintenance.
• Fine control of control rod position by the electric motor reduces mechanical and thermalloads to fuel bundles, thereby increasing fuel reliability.
• Fine control of Control Rod position by the electric motor improves the load following
capability of the plant electric power output.
• Simultaneous drive operation of control rods (gang mode operation) shortens the start uptime of the plant.
• Reduction of the number of FMCRDs to be inspected shortens the time required for
periodical inspection and radiation dose at refueling outages.

Control Rods

FMCRD before assembling

Hydraulic Control Units
21

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Control Rod

FMCRD

Motor
From
electricalsystemHCU

N2bottle

Scram
Valve

Chargingline

ReactorPressure
Vessel

Accumulator

CRD Pump

Flow
Control
Valve

Purge
line

CRD System Configuration

FMCRD Upper
Portion

FMCRD Lower
Portion22

ABWR Structure, System and Component

Nuclear Fuel
Optimized Design and Performance
The enhanced design of the GNF2 fuel assembly ̶ based on pioneering technologies developed by
GNF ̶ provides customers with improved fuel utilization and increased performance and reliability.
In addition to increased output and reduced fuel costs, the GNF2 advanced design offers the latest
technology in corrosion and debris resistance. The advanced debris filter, the Defender™, is now standard
on the GNF2 fuel assembly ̶ increasing reliability and filtration to the best available in today's market.
The GNF2 fuel assembly has undergone rigorous testing and is expected to be even more reliable than otherfuel designs ̶ preventing more fuel failures than any other design due to the standard Defender™ filter.
Increased Energy

・Supports 24 months operation at 120% power
・High exposure capability(up to bundle average 60MWd/t)・High Energy Bundle(High Fuel mass, High Enrichment pellet)
Operating Flexibility ・Increased Critical Power(High performance spacer design)
・Increased Mechanical Power Margin
・Low Pressure Drop(Low pressure drop UTP※1 design)
Fuel Reliability
・Debris Resistance( Advanced Debris Filter - DefenderTM LTP※2-)
・Hydrogen Resistance(Corrosion Resistance Cladding -GNF Ziron- )※1 UTP : Upper Tie Plate , ※2 LTP : Lower Tie Plate

Fuel Assembly Channel Box

Spent Fuel Storage Rack
23

Fuel Assembly(Step2)

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Evolution of BWR Fuels

GNF2 Low Pressure Drop UTP

GNF2 High Performance Spacer
Defender™

GE14

GE14 & GNF2 Defender™ LTP
Improved Debris Protection

GNF2■Operational Optimization - N-Streaming Recognizes Current Design Limitations

Two Stream Design

Six Stream Design

・Traditional designs use 1-2 bundle types
・Local design requirements dictate bundle
characteristics
・Same bundle uses in non-limiting locations
Base
U Rod
Gad+U Rod
Δvs. Base
Base

Expands Design Space・Generate numerous bundle types from anequivalent set of rod types
・Perform core design using fuel rods versus
the fuel bundles
・Solve local problems with unique designs

24

ABWR Structure, System and Component

Turbine and Generator
Hitachi Turbine and Generator, Responsive to the World’s Needs
Since manufacturing the first unit in 1933, Hitachi, Ltd. has supplied numerous turbine
generators to power stations throughout the world. These turbine generators are known for theirhigh levels of efficiency and reliability.
Hitachi has the integrated capacity to supply power stations with all critical deliverables frommaterials for construction to equipment for operations.
Experts in power and electrical equipment, Hitachi not only provides turbine generators but also
instrument and control equipment. Further, Hitachi is able to manage and control turnkey
projects of power stations, including basic planning, design engineering, transportation,
construction work, operations and other related work.
We believe that Hitachi’s total capacity of supplying turbine generators and other equipment isof great benefit to the customers throughout the world.

Shimane 3, Nuclear Turbine

Shimane 3, Nuclear Turbine
25

Installation of Turbine

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Hitachi Steam Turbines
Hitachi Steam Turbines play an important role as a main facility of the electricity generation
business. Hitachi Steam Turbines lead the business with many superior features such as
high-performance long blades by loss reduction technologies and the Ultra Super Critical Steam
Conditions (Steam pressure of 25MPa and Steam temperatures at 600℃/620℃）.

ABWR 60Hz TC6F-52 Turbine■Hitachi Large Generator
It is now more than 90 years since Hitachi's reliable generators first debuted, yet Hitachiinnovation has never slowed.
Today Hitachi produces broad range of superior generators up to 1.6GVA class nuclear turbine
generators.

Shimane 3, Generator Stator

Shimane 3, Nuclear turbine Generator
26

ABWR Structure, System and Component

Advanced NUCAMM-90ABWR Instrumentation & Control Systems
Hitachi’s High Reliability Supports the Stable Operation of Nuclear Power
PlantsHitachi is committed to continuous improvements in the ease of operation and reliability of its
nuclear power plant monitoring and control systems. We are working on increased reliability inthe form of standardization of our digital control panels, and the increased utilization of multiple
technologies and fault tolerance improvement technologies, as well as the use of opticalmultiple transmission technology in the creation of hierarchical information networks.
Our integrated digital monitoring control system, NUCAMM-90, incorporates a background ofdigital technological development and expanded calculation capacity with a high level humaninterface and increased scope of automation.

Main Control Room Overview

27

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Advanced NUCAMM-90 ABWR Instrumentation & Control Systems(NUCAMM-90 : Nuclear Power Plant Control Complex with Advanced Man-Machine Interface 90)●Large-Scale Display Board Facilitates Sharing of Information
Overall plant status supplied as shared information.
Warnings are displayed using hierarchies, for improved identification.
●Compact Main Control Board
Main monitoring operations consolidated into a compact console.
●Expanded Automation Reduces Load on Operator
Expanded automatic operations, including control rod operation, allows operators mainly overall plant monitoring
operations.
●Integrated Digital Control System
Improved reliability and ease of maintenance as a result of integrated digitalization, Electrical and physicalseparation between safety systems and non-safety systems

Main Control Room Control Board
FMCRD: Fine Motion Control Rod Drive

GW

GW

SafetyProtection
SystemNeutronMonitoring
System: Optical Multiplex Transmission

Radiation
Monitoring
SystemRod Control
andInformation
SystemRecirculation
Flow Control
SystemMultiple
Transmission

Plant Computer System: Hard Wired

Feedwater
Flow Control
SystemReactor
Auxiliary
Control
SystemMultiple
Transmission

ReactorTurbineControl
System

TurbineAuxiliary
Control
SystemMultiple
Transmission

TurbineGenerator
Condenser

SafetySystemFMCRD Motor
Control Circuit

Internal Pump Motor
Speed Control Circuit

Feedwater Pump

Condensate
Pumps
GW : Gateway

Defence-in-Depth
Design Philosophy

28

ABWR Structure, System and Component

Radioactive Waste Processing Systems

Gaseous
Waste

Classification of Radioactive Waste and Process Flow
Off GasTank Vent Gas

Solid Waste

Liquid Waste

LCW
HCW

Discharge

 Recombination
 Noble Gas Hold-up
 Iodine Removal
 Hollow–Fiber Filtration
 Demineralization
 Evaporation
Concentrated
liquid waste Volume Reduction /Solidification

L/D, S/D Filtration(Evaporation)
Incineration

Non-Combustible
Waste

 Compaction /Solidification

Sludge Storage Tank

RecycleSolidification

Spent Resin

Combustible Waste

Discharge

Ash

CR/FCB .etc…

 Site Bunker

Spent Fuel

 Spent Fuel Storage Pool

Waste
Drum
Inspection

Storage

Disposal

Discharge

Solidification

LCW : Low Conductivity
Waste
HCW : High Conductivity
Waste
L/D : Laundry Drain
S/D : Shower Drain
CR : Control Rod
FCB : Fuel Channel Box■Gaseous Waste Processing System
Off Gas Recombiner fitted with a Sponge-Metal Catalyst
to achieve high recombination efficiency
Noble Gas Hold-up unit with a simplified and compact
designSilver-Alumina Adsorbent used to achieve high Iodine
removal efficiency
Off Gas Recombiner Module＊This figure shows an example of existing Japanese plant module＊Two recombiners are installed in the latest ABWR design■Liquid Waste Processing System
Hollow Fiber Filter with highprocessing capability
Secondary waste generation reduced byhalfBy combining Hollow Fiber Filtration
with a Demineralizer, processed liquid
can be reused or discharged to theenvironment
29

Hollow Fiber
Filter Element

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Waste Solidification System
Cement based solidification materials, improved mixer efficiency to achieve stable solid waste
Overview of Solidification System
HopperHigh Activity
Sludge Slurry

Dewatering Machine Hopper

Cententrated
Dry Powder

In-Drum Mixer
Solidification
InDrumMixer

Solidified
Waste

In-Drum Mixer

FeaturesCover Minimization of secondarywaste Improved mixing efficiency

HopperWashing
Spray Ring

Ash (Incinerator)
OutDrum
Mixer

Compactible
Solid Waste

CementPaste

High Speed
Blade

Solidified
Waste

Supercompactor

NonCompactible
Solid Waste

200L Drum

Empty Drum

Planetary
Blade■Site Bunker Facility
Overhead Crane

FeaturesStainless Steel Lined PoolHigh Density Storage Rack
Fitted with a high-level waste
Volume Reduction Equipment
Diversified Pool Water Cleanup
SystemPool water
Filter/Demineralizer

Cask
Truck

High Activity Waste
Volume Reduction Unit

SludgeStorage Tank

Surge
Tank

Cask
Decontamination
Unit

Pool Water Circulation Pump

■Waste Drum Inspection System
Features

Proven performance in BWR/PWR
plantsCompact System
Fully automated handling and dataprocessing
High maintainability

Weight, Activity and Dose rate
Measurement Units
30

ABWR Structure, System and Component

Automatic Equipment
Remote-Automatic Equipment to Reduce Radiation Exposure and Manpower
To reduce radiation exposure and manpower, Hitachi has developed many remote-automatic
maintenance and inspection equipment based upon proven robotic technologies.

■Refueling Machine
Nuclear fuel is exchanged with new fuel during reactor shutdown to form the new reactor core.
The refueling machine that performs this fuel exchange operation travels or moves laterally over
the reactor well and spent fuel storage
pool to move the fuel.
The automatic refueling machine,developed by Hitachi, performs thisoperation with high precision by using aprocess computer that automaticallycontrols the speed and position of therefueling machine in four-dimensions;bridge travel, trolley travel, grapple
vertical and rotational. By simple
operation instructions from the remotecontrol room, the refueling operation canbe done swiftly and safely.

■RIP (Reactor Internal Pump) Maintenance Equipment
Pull Up
Grappling tool
RIP Impeller
Pressure Seal

Guide screw
RIP Motor

Guide screw
mounting lug

Nut

Pull Down

Assembled Condition

31

Raising/Lowering
DeviceClosing Flange

Motor Removal

Impeller Removal

RIP Maintenance Equipment is roughly divided
into the Elevator withguide screw under
vessel and the grappling tool on the refuelingfloor. The elevator isdriven by electrical motorthat raises and lowers
RIP motors.
Grappling tool is connected to RIP hoist ofRefueling machine tohandle the Impeller.

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■CRD Handling Equipment
During the periodic reactor inspection, the FMCRD is inspected
and maintained.
FMCRD handling work is performed with the CRD Handling
Equipment installed undervessel for it’sassembling/dis-assembling. Then, the dis-assembled FMCRD isinspected/maintained with Maintenance Equipment.

■Fuel Preparation Machine
Loading preparations of new fuel and inspections of used fuelare performed under water using a fuel preparation machine.
At Hitachi, development and practical use have beenaccomplished of an Improved Fuel Preparation Machine, notonly with remote control and electric motor drive, but also witha new structure for ease of maintenance and inspection.

■In-Service Inspection Equipment
This equipment is used to detect defects on the outer RPV (body,support skirts, flanges, nozzles and their corners), pipes and RIP
nozzles by using ultrasonic probes.
In consideration of the broad range of thicknesses and number ofsteel grades to be inspected in the RPV and pipe, an incidence
angle fixation probe is utilized. However, for the RIP nozzle, aphased array probe is used.
32

Project Management Organizations

Organization for Hitachi's Nuclear Buisiness
Hitachi's Unified Company-Wide Nuclear Business System Based on
Hitachi Technology
Together with all partners in the Hitachi group, Hitachi-GE Nuclear energy has established acomprehensive line-up of nuclear power service including planning, design, manufacturing,
installation and maintenance of nuclear power generation plants; furthermore, we also provide
training programs for plant operators. At present, Hitachi is making diligent efforts to further improve
the related technology through the introduction of economically efficient light water reactor and thepractical use of fast reactor while continuing to promote research and development.

Hitachi-GE Nuclear Energy,Ltd.
Registered Office

Tokyo HQ

Rinkai Factory
Nuclear power plant components
Hitachi Works

Internals

Akihabara Daibiru

Hitachi, Ltd. Power Business Unit
power transformers,
breakers, etc.

Power Production Management Division (Kokubu Production Division)

Transformer

Service & Platforms Business Unit
Instrumentationand controls,
control panels,
control computers,
etc.

Control System Platform Division (Omika Works)

Main Control System

Industrial Products Business Unit
Pumps

Machinery Systems Division (Tsuchiura Works)

33

Reactor Internal Pump

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Affiliated Companies
Generator

Steam turbines,
generators

TurbineReactor pressure
vessel, etc.

Mitsubishi Hitachi Power Systems, Ltd.

Reactor Pressure Vessel

Hitachi Plant Construction, Ltd.

Planning and execution ofsite installation

Global Nuclear Fuel-Japan Co., Ltd.

Fabrication work of nuclear
fuel

BWR Operator Training Center Inc.

Training of operators

Nippon Nuclear Fuel Development Co., Ltd.

Development of nuclear fueland related technology

Hitachi Industrial Equipment Systems Co., Ltd.

Switch boards

R&D

Hitachi Reseach Laboratory

Studies concerning reactor
safety analysis, waste
treatment, instrumentation,and control
Energy and Environmental Systems Research Center

Development of materials

Materials Research Center

Studies concerning seismic
designMechanical Engineering Research Center34

Project Management Organizations

Engineering Technologies
Concept to Reality- HITACHI‘s IT Technologies Streamline Nuclear Plant Life-long Management
The design stage of nuclear power plant requires overall coordination of broad range ofengineering tasks, including conceptual design, layout design, equipment carry in/out plan,shielding plan, as well as the plant construction, operation and maintenance plan.
Schedule management, workforce management and QA/QC management are also importantduring each task phase.
In order to perform these tasks efficiently, Hitachi has developed an "Advanced Integrated CAE
System" to actualize high-quality and efficient works.
This system works based on not only the plant engineering database but also the accumulated
experiences and management know-how of the previous projects.
Also, it is enhanced day by day through the actual projects as our core in-house engineeringsystem.

Conceptual& Basic
Design3D Modeling& Detail
DesignProduction
Design &Manufacturing

Plant Engineer
EPC Project Experience / Pro
35

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

Our Policies• Execute as planned• Simulate in advance• Highest quality and safety• On schedule/on budget• Ultimate plant usability;-Constructability-Operability-Maintainability

Construction&
Start UpOperation&
Maintenance

Reactor
Decommission-ing planing Database
ject Management Know-How
36

Project Management Organizations

Construction
Hitachi’s Proven NPP Construction
To improve the construction period, safety and quality, Hitachi has continuously improved its
construction technologies since the first BWR Nuclear Power Plant (NPP) construction in1970’s. Now, Hitachi has 4 main construction strategies.
These strategies contribute to Hitachi’s excellent execution of NPP projects.

NPP Construction

Safe / Quality / On-Schedule / On-Budget

Open-top &Modularization
ParallelConstruction
with Very Heavy
Floor Packaging
Lift Crane

Front-Loaded
Integrated
Construction Engineering
Construction
Detailed Schedule
Management
SystemManagement

r
fo

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R/
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BW
o
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C
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Op ctio
Reactor Building
Base-Mat Composite
Module

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Co th T ne
wi Cra

37

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E• all d B ctiru
Pa nde nstra
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Large Module
Installation by VHL※
(Weight : 650 MT)※VHL : Very Heavy Lift

!

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dv olog d M od
A• hn ize thcedTe dar n M
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Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

’s
nt
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a
M
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&
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B
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4D Visual Construction System
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Plan

Implement
Open‐Top Construction

Visualized Construction Sequence(Front‐Loaded Engineering)38

Project Management Organizations

Quality Assurance System
Hitachi Guarantees the High Quality of the Products, which are Supported by
Hitachi’s Time-Tested Array of Technologies
In order to ensure construction of high quality, highly reliable nuclear power plants, Hitachi hasestablished a consistent quality assurance system, which extends to design, manufacture,inspection, installation, and even preventative maintenance after delivery.
In addition, ISO9001 certification was first obtained in 1999.

The Manufacture of Nuclear Power Equipment Requires Advanced Technology■Nuclear Power Quality Assurance System
Hitachi-GE Nuclear Energy, Ltd. Nuclear Systems Quality Assurance Division■Nuclear Power Quality Assurance Activities
Nuclear Power Quality Assurance Committee

Hitachi-GE Nuclear Energy, Ltd. Hitachi Works
Nuclear Power Project Administration Regulations
Local Construction Site / Office
Nuclear Power OCHIBO Committee
Hitachi, Ltd.
Power Systems Company

Nuclear Equipment Accident Prevention Committee

Thermal Power Systems Division

Construction Plant Reliability Activities

Power & Industrial Systems Division

Operation Plant Reliability Activities⁝

Infrastructure Systems Company

Research Institutes
Related Companies, etc.

39

Various
Quality
Assurance
Departments

Various
Quality
Assurance
Departments

Various Reliability Improvement Activities

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■QMS operation for Plant Delivery
Quality management system at Hitachi-GE and the Hitachi Group
PDCA cycle used in Hitachi-GE’s QMS

QMS and Hitachi Group companies(The activities shown in the diagram are typical example)

Hitachi Works, Hitachi, Ltd.
(Thermal power/industrial division,
Kokubu Production Headquarters)
Hitachi, Ltd.
Information & Control Systems Division
Kure Division, Babcock-Hitachi K.K.
Hitachi Plant Technologies, Ltd., etc.

Management review
Act[Analysis and improvement]
Analysis of accidents andfailures
QF Plant Committee

Resource
management

Plan[Management responsibilities]
Nuclear facilities
Quality policies
Quality objectives(business plan)Do
PDCA cycle for product realization
Plan

Act
Check
[Monitoring and measuring]
NZD activities
QF task activities

Data analysis
improvement

Estimate andcontract work
plan

Check
Inspection andtesting
Control of nonconformity

Do
Design,manufacture,
installation,
maintenance

Act

Plan

Check

Do

Note) NZD: Nuclear Zero Defect, QF: Quality First■Quality Control Activities
Research andDevelopment
Design
Reviews

Internal Audits

Inspection

Planning
Design
Reviews

Preventative
MaintenanceImportant Point
Check for Periodical
Inspection /Prior
Modification
Reviews

Periodical Inspection

Design
Reviews

Technical
Supportfor Operating
Plants

Pre-Operation

Prior
Reviews

Validation

Prior
Reviews

Overall
Construction
Inspection

Internal Audits

DesignVerification Component
Testing

Design
Reviews

Purchasing
Prior
Reviews

Manufacture

Inspection

Inspection of
Suppliers

Inspection

Installation40

Project Management Organizations

Preventive Maintenance
Hitachi’s Preventive Maintenance Technologies ensure Optimum Performance
Hitachi offers high valued service with the most advanced inspection, stress relaxation, andrepair technologies, utilizing our abundant product manufacturing experience and IT in order tocontribute to the high reliability of nuclear power plants.

■Hitachi BWR Reactor Preventive
Maintenance Technology Center■Inspection Technologies
Hitachi has developed various inspection technologies
and systems.
Sensing Technologies (UT, ECT, RT)
Developing many sensors and inspection systems adapted for various
materials, shapes and environments, and use them in the real plants.
FBH Echoes
70mm
BottomEcho

CAD of φ2mm and φ1mm FBH

FBH

FBH : Flat Bottom Holes

Flexible Multi Coil ECT Sensor

Inspection Mechanics and Systems
Developing and use remote andautomated inspection equipment for the
nuclear power plant facilities.

Pipe Inspection System
Scanner

Power Cable

ThrusterCut View of Pit
Hitachi's underwater technicians can train themaintenance works remotely 20 meters above thebottom of RPV or below a forest of structures under
RPV in the simulated facility.

41

Running wheel

Skirt

Remotely Operated Underwater Vehicle(Extraction Type)

Remotely Operated
Underwater Vehicle(Swimming Type)Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Stress Relaxation Technologies
Hitachi's stress relaxation technologies improve the reliability of nuclear power plants.
Stress Improvement of Inner surface of pipes by
Induction Heating Stress Improvement (IHSI)

Stress Improvement of RPV Internals by
Water Jet Peening (WJP)

Test loop

WJP
nozzleInduction
Heating System

Heating coil■Repair Technologies
Hitachi has developed and applied various repair technologies and systems.
Remote Repair Technology of RPV Bottom Head Equipment

Welding
Torch

Positioning
Head

Welding
Work

PositioningHead
3-D simulation

Manipulator

42

Research and Development

Research and Development
Multi-purpose steam source test facility (HUSTLE)
Hitachi is accelerating R & D to develop superior technology and products in its key nuclear
businesses of new plants, components, maintenance, and uprates, making full use of the test
facility which provides two phase flow under BWR's actual pressure and temperature.

■Features・One of the biggest facilities in Japan
・BWR's actual operating condition (Up to 7MPa/290℃)
・Two-phase flow
・Steam recirculation with steam compressor

⑤

⑥

①

①Test section②Water heater③Steam heater④Steam compressor⑤Condenser⑥Control room③②④

Layout of the facility

System configuration⑤①

Test center of HUSTLE③②④

HUSTLE:Hitachi Utility Steam Test Leading facility
3D Cut Model of the Steam compressor
43

Our highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■Testing
Various tests are performed to confirm performanceand quality of nuclear core equipment.

Reactor Internal Pump Test Facility

Reactor Internal Pump

Reactor Pressure
VesselHigh-Performance Test Facility ofControl Rod Scrammability under Seismic
Conditions
High-Performance Control Rod Seismic Scrammability Test Facility
Shakers5m
Floor Level

12m

Reaction Wall・This test facility can performseismic scrammability tests for all
BWR type reactors.
・Parallel and horizontal excitation
Seismic Isolatorsby two hydraulic shakers candemonstrate seismic response
behavior.
Hydraulic Pumps
・Seismic isolators are used forsupporting the reaction wall in
4 Fuel Assemblies, 1 Control Rod Drive,
order to minimize the vibration
1 Control Rod, and Test Vessel
influence to the surrounding
areas.
44

Achievements

Hitachi's Achievements in Nuclear Power
Hitachi is Committed to Apply the Latest Technology to Construct Advanced
Power Stations
Since we took part in the construction of Japan’s first light water reactor -The Japan Atomic
Power Co.’s Tsuruga Nuclear Power Station Unit No.1- Hitachi has installed 20 nuclear power
plants in total. We are also in the process of constructing a further three plants.
■Achievements in Nuclear Power Plant Delivery
Electric Power Development Co., Ltd.,
Ohma Nuclear Power Station(Under construction)■JapanTokyo Electric Power Company Holdings, Inc.
Higashidori Nuclear Power Station
Unit 1(Under construction)

Tokyo Electric Power Company Holdings, Inc.
Kashiwazaki-Kariwa Nuclear Power Station
Unit 4 ('94), Unit 5 ('90),
Unit 6 ('96), Unit 7 ('97)

Tohoku Electric Power Co., Inc.,
Onagawa Nuclear Power Station
Unit 3 ('02)

Hokuriku Electric Power Co., Inc.,
Shika Nuclear Power Station
Unit 1 ('93), Unit 2 ('06)

Tokyo Electric Power Company Holdings, Inc.
Fukushima Nuclear Power Station I
Unit 1 ('71), Unit 4 ('78)

The Japan Atomic Power Co.,
Tsuruga Power Plant I('70)

Tokyo Electric Power Company Holdings, Inc.
Fukushima Nuclear Power Station II
Unit 2 ('84), Unit 4 ('87)

The Chugoku Electric Power Co., Inc.,
Shimane Nuclear Power Station
Unit 1 ('74) (Closed down)
Unit 2 ('89)
Unit 3 (Under construction)

The Japan Atomic Power Co.,
Tokai Power Plant 2('78)
Chubu Electric Power Co., Inc.,
Hamaoka Nuclear Power Station
Unit 1 ('76), Unit 2 ('78), (Closed down)
Unit 3 ('87), Unit 4 ('93), Unit 5 ('05)
Operating( ) : Year of commercial operation
Under construction
Under decommissioning, Closed down■Overseas
South Korea
Generator replacement
Kori

U.S.
Nuclear reactor pressure vessel
Hope Creek ('74)
PLR & RHR piping replacement
Vermont Yankee ('85)
PLR & RHR piping replacement
Peach Bottom ('85)

EuropeCore internals
Leibstadt ('80)

Pakistan
Turbine power generator
Karachi ('72)
China
Turbine power generator, condenser,
moisture separator/heater, etc.
Qinshan III unit 1, 2ThailandRadioactive Waste Treatment System
Ongkharak Nuclear Research Center

45

Taiwan Region
Reactor containment vessel
Chinshan unit 1, 2 ('73, '74)
Spent fuel storage rack
Chinshan unit 1, 2 ('78)
Spent fuel storage rack
LungmenRadioactive-waste disposal facility
Water treatment system

Operating( ) : Year of delivery
Under planning / ConstructionOur highly reliable products, based on proven design, are leading nuclear technologythat enhance the safety of nuclear power plants.

■History of Hitachi’s Nuclear Power Plant Construction
1970
Decade1980

Change Over from Imported
Reactors to Domestic
Reactors

1990

2000

Improvement & Standardization Program

2010

Advanced Boiling Water Reactor

Higashidori 1 *(Tokyo Electric Power Company Holdings, Inc.)

Under
Construction

Ohma *(Electric Power Development Co., Ltd.)

Under
Construction（kWe）
20,000,000

Shimane 3(The Chugoku Electric Power Co., Inc.)

Under
Construction

Shika 2
(Hokuriku Electric Power Co., Inc.)
Hamaoka 5 *(Chubu Electric Power Co., Inc.)
Hitachi has
installed a totalof 20 power plants
15,000,000

Onagawa 3 *(Tohoku Electric Power Co., Inc.)

18,811,000 kWe

Kashiwazaki-Kariwa 7 *(Tokyo Electric Power Company Holdings, Inc.)
Kashiwazaki-Kariwa 6 *(Tokyo Electric Power Company Holdings, Inc.)
Kashiwazaki-Kariwa 4(Tokyo Electric Power Company Holdings, Inc.)
Hamaoka 4 *(Chubu Electric Power Co., Inc.)

10,000,000

Shika 1 (Hokuriku Electric Power Co., Inc.)

Facility
Capacity

Kashiwazaki-Kariwa 5 (Tokyo Electric Power Company Holdings, Inc.)
Tsuruga 1*(The Japan Atomic Power Co.)

5,000,000

Shimane 2 (The Chugoku Electric Power Co., Inc.)

Fukushima Ⅰ-1*
(The Tokyo Electric Power Co., Inc.)

Hamaoka 3 *(Chubu Electric Power Co., Inc.)

Shimane 1(The Chugoku Electric Power Co., Inc.)

Fukushima Ⅱ-4 (Tokyo Electric Power Company Holdings, Inc.)

Hamaoka 1*(Chubu Electric Power Co., Inc.)

Fukushima Ⅱ-2 (Tokyo Electric Power Company Holdings, Inc.)

Hamaoka 2 *(Chubu Electric Power Co., Inc.)
Tokai Ⅱ *(The Japan Atomic Power Co.)
Fukushima Ⅰ-4 (Tokyo Electric Power Company Holdings, Inc.)

0*：Joint construction project46

Address: 1-1, 3-chome, Saiwai-cho, Hitachi-shi, Ibaraki-ken, 317-0073 JapanTokyo Head Ofwce

Phone: +81-294-22-1000

Akihabara Daibiru Building, 18-13, Soto-Kanda 1-chome, Chiyoda-ku, Tokyo, 101-8608 Japan
Phone: +81-3-4564-3947

Catalog No. : 83Z-Z1-0022 R5
Reprint without Permission Prohibition
Printed in Japan 2018.05© Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved