Innovative Light-Water Reactor

See the following for more information
about the HI-ABWR:
www.hitachi-hgne.co.jp/en/abwr

https://www.hitachi-hgne.co.jp/en/
Address: 1-1, 3-chome, Saiwai-cho, Hitachi-shi, Ibaraki-ken, 317-0073 Japan

Phone: +81-294-22-1000

Akihabara Daibiru Building, 18-13, Soto-Kanda 1-chome, Chiyoda-ku, Tokyo, 101-8608 Japan
http://www.hitachi-hgne.co.jp/en/index.html

Catalog No. : 83Z-OG-0051(R1)
Reprint without Permission Prohibition
Printed in Japan 2024.2

Innovating toprotect the f uture
The highly Innovative ABWR (HI-ABWR) is based on aninternational standard of ABWR design that meets theregulatory requirements of the UK and Europe hasreceived design acceptance conﬁrmation from the UK,
reﬂecting lessons learned from the Fukushima Daiichi
Nuclear Power Station accident. The HI-ABWR is anext-generation light water reactor that incorporates newsafety mechanisms.
It is equipped with innovative safety features, such as disastercountermeasures, control of unexpected accident escalation
and reduce the reactor's impact on the environment.
In addition, it contributes to the realization of carbon
neutrality through the reduction of spent fuel using highburnup fuels and the stabilization of electric power systems
by load following operations.

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2Protecting from disasters
The HI-ABWR is designed to address various disasters including earthquakes and tsunamis
and physical impacts due to airplane crashes, internal fires and floods. The HI-ABWR
minimizes the impact of disasters by strengthening the exterior wall and safety-divisional
separation barrier.

Strengthening robustness against impacts and disasters

Pursuing resilience ofbuildings and equipment

Strengthening buildings against airplane crashes

Toughening buildings

The exterior wall of the reactor building is designed

The robust exterior wall is built to be robust in the event

to withstand airplane crashes and minimizes not onlyof a physical impact due to airplane crash, etc. and is

the area of physical impacts but also the range ofalso seismic resistant, protecting the building fromvibration propagation after an airplane crashes.

physical damage and earthquake-caused damage.
Maintaining safety and limiting the increase in building
materials improves economic efficiency.

Seismic-resistant construction basedon lateral restraint
In addition to the reinforced concrete constituting thebuilding, lateral restraint using rocks and backfilling earth
Simulation of an airplane crash into the reactor building

around the building strengthen its anti-seismic capabilities.

Improving seismic-resistance performanceby lowering the center of gravity andhighly aseismic design

Minimizing the area of the impact of disasters
In order to prevent significant damage to the reactor
core during an accident, the safety systems for

The center of gravity of the overall building is lowered

design basis accidents and the safety systems forby installing heavy equipment on the lower floors andsevere accidents, are located in four areas separated

reducing the slab above to upgrade aseismic

using fire-resistant, water shut-off walls to minimize

capabilities. Highly aseismic design is adopted in

the impact of internal fires and flooding caused byequipment as well as the building to improve thepipe breaks to each area.

seismic resistance of the entire power plant.
Air-cooled
gas turbine
generator

Water
injection
pump

Used for both measures to strengthen buildings
against airplane crashes and measures toimprove seismic resistance performance

Reactor pressure
vesselThe safety systems for SA*1
The safety systems
for DBA*2
Div. AThe safety systems
for DBA*2
Div. B

Water
injectionpump

The safety systems
for DBA*2
Div. C
Reactorbuilding

Use of lateral
restraints

Emergency
dieselgenerator

Low centerof gravity
for equipment*1 The safety systems for SA…The safety systems for severe accidents*2 The safety systems for DBA…The safety systems for design basis accidents)JHIMZ*OOPW BUJWF (VBSE34Preventing accidents escalation
A passive safety system is a system that incorporates mechanisms driven using naturalforce without relying on an external power supply or the actions of operators toSuppressing the accident escalation
without an external power supply

mitigate the impact incurred should an accident occur.
The HI-ABWR introduces a passive core cooling system, lower drywell ﬂooder,containment system for radioactive substances (ﬁlter vent system + noble gas ﬁlter +new iodine ﬁlter etc.) to suppress the accident escalation

Passive reactor cooling system driven by
the difference in the density of water andsteam and the height difference withthe reactor pressure vessel

and reduce the impact on the environment.
The cooling water source, which is installed at a higher
elevation than the reactor pressure vessel, cools thesteam from the reactor and circulates it to cool the core.

Confining radioactive substances toreduce their impact on the environment

Due to automatic activation, 24-hour operation by
operator actions are not required.

Containment system for radioactive substances,which reduces their impact on the environment

Cooling water source.

Reactor pressure
vesselIn addition to the conventional filter vent system for
Steam inthe reactor

reducing emissions of radioactive substances into theenvironment, a noble gas filter and a new iodine
filter--the latter capable of removing organic iodine,
traditionally difficult to remove--have been installed toremove radioactive noble gases and organic iodine
from the steam and hydrogen emitted into the air. This
helps reduce the need for resident evacuation even if aLower drywell flooder that does notrequire operator actions

severe accident were to occur.
Reactor pressure vessel

Should a core be damaged and molten fuel (debris) fall
Discharge

Steam/hydrogenfrom the reactor pressure vessel, the fusible plug valve
is activated by the radiation heat of the debris andFilter vent system(Removes cesium
and other ﬁssion
products)

other attributes, causing coolant to be injected using
gravity. The coolant is able to cool the debris for threedays. Furthermore, a core catcher is provided toprevent floor erosion caused by the debris.

Noble gas ﬁlter(Removes nitrogen/noble gases)

New iodine ﬁlter(Removesorganic iodine)･ Steam･ Hydrogen･ Nitrogen･ Fission products

Suppression pool (S/P)
Fusible plug valve

Core catcher)JHIMZ*OOPW BUJWF4BGFUZ
56

Protection using digital technology

Sustainably protecting society

Hitachi's Lumada is a new approach that connects humans, digital technology and otherIn order to realize a sustainable society, stable supply of electricity is required while reducing

technologies.

environmental impact, realizing carbon neutrality, and utilizing renewable sources of energy.

Plant monitoring and operation, as well as maintenance are enhanced by utilizing

We are making further improvements such as development of new fuels, operations thatknowledge of the latest digital technologies. In addition, the instrument and control

stabilize electric power systems and the improvement of capacity factor throughequipment is arranged in multiple locations to ensure safety against a single failure, andmaintenance.

prepared for accidents in various ways as necessary.

Next-generation central control room based on the harmony ofhuman and machine

Improving operation costs using high burnup fuels

human performance that have been

Average removal
burnup level（GWd/t）

implemented in the past and the digital

60

innovation focused on the accumulated

55

know-how and data, monitoring and50

operations are ensured in normalcveuse
ourchieres nium,・ A c tive
rauef
ﬀog
・E
inuc
(redcreated, combining equipment25

used. High-performance high burnupup
fuels enable extended cycle operation,ion,

GNF3 fuel (10 x 10 fuel)reducing operating costs and spentt fuel.

Step II fuel (8 x 8 fuel)3530recently designed fuels can always beStep III fuel (9 x 9 fuel)45

equipment management, a digital twin isbackwards-compatible, the mostcyp raelcy• U ndedg fu ﬃcien
tenupesuin• Exbur tion
Enriched
ultrahigh burnup fuelPu r o m i c
dasen
rea
tiliz of Pu)(there are achievements overseas)ince coeu40

operations and during accidents. For

Since BWR fuels arefo rt io n l ant
cy"
liza
U t i uing p ﬃcien
ers" Pu o m i cnnratio
opee c o tecle

With the consideration of factors affecting

Step I fuel (8 x 8 fuel)New 8 x 8 fuel

1970

1980

1990

GNF3 fuel*
2000

2010

2020

2030

2040 (FY)management and Lumada. The migration* GNF3 fuel: Next-generation fuel assembly
developed by Global
Nuclear Fuel (GNF)from construction management toequipment management will be seamless.

Central control room (for illustrative purposes)

Stabilizing electric power systems through load following operations
When the power generated from

Instrument and control equipment for risk management
For instrument and control equipment

renewable energy sources increases,（%）

CloudySunnyPlant monitoring80

severe accidents has been confirmed in60

environment testing.
Control system

backups by diversified equipment isaddressed to the risk of failure due toco-factors in digital systems.

Thermal,etc.

enable the fine control of electric power
output and thus, help stabilize electric
power systems through load following

Nuclear40

Defense against cyberattacks is provided
using one-way communication, andSafety systemand surplus power is generated. BWRs

exposed to a harsh environment, set upequipment whose performance against

200

electric power systems become unstable

Electricity demand

100

Data diodeCloudyoperations.

Solarpower
Hydro, wind andgeothermal

The amount of power
produced by solar power
generation facilities varies
depending on the weather

Reduce dependency onthermal power generationand contribute to carbon
neutrality

BWR's ability to ﬁnely
adjust power generation
enables the generation ofpower according todemand

Realizing stable operation through the consideration of maintenance
Designed to streamline maintenance and reduce downtime required for plant maintenance, helping toimprove capacity factor.

)JHIMZ*OOPWBUJWF4FDVSJUZ7)JHIMZ*OOPWBUJWF4VTUBJOBCJMJUZ
8Hitachi's evolving BWR technologies

Nuclear power plant delivery record

Electric Power Development Co., Ltd.,
Ohma Nuclear Power Station(Under construction)
Tokyo Electric Power Company Holdings, Inc.
Higashidori Nuclear Power Station

Hitachi's BWR technologies continue to evolve.
Hitachi's initiatives in the nuclear power business began with a research reactor whichstarted operating in 1957.
Since we started commercial operation of the Japan's first commercial light-water reactor in1970, we have supplied many nuclear plants.
Incorporating the experience from the Fukushima Daiichi Nuclear Power Station accident,
we will promote reliability improvement activities and the development of preventive

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

Unit 1(Under construction)
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) (Closed down)

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) (Closed down)

The Chugoku Electric Power Co., Inc.,
Shimane Nuclear Power Station

maintenance technology and pursue increased safety.

The Japan Atomic Power Co.,
Tokai Power Plant 2('78)

Unit 1 ('74) (Closed down)
Unit 2 ('89)
Unit 3 (Under construction)

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)

History of BWR reactor development and innovative light-water reactors

Operating( ) : Year of commercial operation
Under construction
Under decommissioning, Closed down

BWRX-300

HI-ABWR basic specifications(Small modular reactor)

Item

HI-ABWR(Innovative light-water reactor)

ABWR

1350 to 1500 MWe

Thermal power

3926 to 4300 MWt

Reactor pressure

Approx. 7.17 MPa [abs]Rated core ﬂow rate

Approx. 52.2 x 103 t/hReactor core
• Rational installationof safety equipment• Further reduction ofthe impact of exposure
during accidents• Installationof passivesafety system

Fuels

UK ABWR・ Mitigation of impact of loss ofcoolant accidents (eliminationof the need for water injectionequipment)
・ Rational installation of safety
equipment・ Strengthening against disaster(containment mostlyunderground)・ Installation of passive safetysystem
・ Strengthening of measures toprevent severe accidents

ESBWR

HeightApprox. 3.8 m

DiameterApprox. 5.2 m

Model

10 x 10 fuel (employs the latest fuel at the time of operation)

Level of enrichment

Approx. 4% (adjust based on the reactor cycle length and fuel discharge burnup)

Number of assemblies

872

Reactor pressure vessel Internal diameter x overall height
Number of rods

Basicdesign
Control rod

・Strenthening of measuresagainst severe accidents(International standard ABWR)
and disasters
・Introduction of measuresagainst aircraft crashes

Speciﬁcations

Electric power

Drivesystem

Internal diameter: Approx. 7.1 m, Height: Approx. 21 m
205

At output control

Finely adjusted electromotive drive

At scram

Hydraulic-driven high-speed scram

Control material

Boron carbide (partially hafnium)

Recirculation method
Nuclear reactor
recirculation system Number of pumps

Internal pump

High-pressureEmergency core water injection
cooling system Low-pressure water injection

High-pressure core injection system (2 lines)

Reactor pressure vessel depressurization

10Reactor core isolation cooling system (1 line)
Low-pressure core injection system (3 lines)
Auto-depressurization system

Residual heat removal system

3 linesContainment

Made of reinforced concrete integrated into the building

The safety system for preventing
reactor core damage

Passive reactor cooling system (1 line)

The safetysystem for
The safety system for preventing
severeaccidents containment vessel damage

Substitute low-pressure core injection system (1 line)Fusible plug valve
Core catcher
Containment over pressure protection system
Filter vent system
Noble gas ﬁlter)JHIMZ*OOPW BUJWF " #83910

Innovative Light-Water Reactor

See the following for more information
about the HI-ABWR:
www.hitachi-hgne.co.jp/en/abwr

https://www.hitachi-hgne.co.jp/en/
Address: 1-1, 3-chome, Saiwai-cho, Hitachi-shi, Ibaraki-ken, 317-0073 Japan

Phone: +81-294-22-1000

Akihabara Daibiru Building, 18-13, Soto-Kanda 1-chome, Chiyoda-ku, Tokyo, 101-8608 Japan
http://www.hitachi-hgne.co.jp/en/index.htmlCatalog No. : 83Z-OG-0051(R1)
Reprint without Permission Prohibition
Printed in Japan 2024.2