Technology

By undertaking nuclear power plant projects constantly,
TEAM KOREA has maintained an edge in the global nuclear industry – in both technology and experience.

Korean Nuclear Industry

APR1400
APR1400

US NRC Certified Design

The APR1400 is a Gen 111+ large capacity Pressurized Water Reactor(PWR), generating 1,400
MW of electrical power to comply with US NRC regulations.

Total 5 Units of APR1400 is now in operation both in Korea(4 units) and UAE (l Unit),& 4 units in Korea and 3 units in UAE are under construction. By adopting the proven and advanced design features based on technology enhancement, the APR1400 achieved the Design
Certification(DC)from the US NRC in August 2019.

By achieving NRC approval - the international "Gold Standard - for design and safety - the
APR1400 brings improved public confidence and internationalreputation.

EU-APR Major Parameters
GENERAL
PLANT DATA
Gross Power Output 1,400 MWe
Thermal Power 3,983 MWth
Design Lifetime 60 years
Seismic Design Basis DBE 0.3g
REACTOR
CORE
Active Core Length 3.81 m
Core Diameter 3.65 m
Average Heat Flux at 100% Power 589.1 kW/m2
Number of Fuel Assemblies 241, 16×16
Number of
Control Element Assemblies
81 Full Strength,
12 Part Strength
Fuel Cycle Length 18
REACTOR
COOLANT
SYSTEM
Number of Loops 2
Operating Pressure 15.5 Mpa
Inlet Temperature 290.6℃
Outlet Temperature 323.9℃
Enhanced Safety
Improved Safety Systems

4 Independent Train Safety Injection System

  • Provides borated water to core with Active & Passive Components
  • Fluidic Device installed at the bottom of the Safety Injection Tank (SIT) passively and efficiently controls the safety injection flow into the core

Safety Injection System (SIS) uses injecting water from In-Containment Refueling Water Storage Tank (IRWST)

4 Train Safety Injection System

4 Train Safety Injection System

Fluidic Device

Fluidic Device

Mitigation of Severe Accident

Passive Autocatalytic Recombiner (PAR) & Hydrogen Ignitor

  • Limit Hydrogen Concentration
  • Prevent Hydrogen Detonation

Improved Performance of Containment Spray System

  • Emergency Containment Spray Backup (ECSB) system guarantees the integrity of containment by cooling containment for 48 Hours from one full day after a core melt down

Cavity Flooding System & Corium Chamber

  • Cavity Flooding System prevents basement melt-through
  • Corium Chamber cools molten corium inside the containment

Rapid Depressurization System

  • Safety Depressurization & Vent System, SDVSRapidly reduces the pressure of the reactor coolant system when the pressurizer spray is unavailable during shutdown cooling
    * The Pilot Operated Safety Relief Valves (POSRV) are employed to enable precise operation & easy Maintenance
  • Emergency Reactor Depressurization System, ERDS Applied In-Vessel Retention & Ex-Reactor Vessel Cooling(IVR-ERVC) System
Hydrogen-Air Mixture > Hydrogen-Removed Air / Hydrogen-Air Mixture > Porous Catalyst > Hydrogen-Removed Air

Passive Autocatalytic Recombiner

RCS, Aux,Building, CVCS, BAMP(200gpm), SCP(5000gpm), IRWST, Cavity, HVT, IRWST, Containment Building Reactor Coolant System, Gravity Driven Caviry Flooding System For Ex-Vessel Cooling (Passive Feature), External Reactor Vessel Cooling System For In-Vessel Retention(Active Feature)

Passive Autocatalytic Recombiner

Provisions for Beyond Design Basis External Events

Enhanced design against Beyond Design Basis External Events(BDBEE),
incorporating Fukushima accident lessons learned

  • Phased core and spent fuel pool cooling strategy
  • Enhanced containment capability to LOCA
  • Diverse & flexible supporting system
  • Enhanced design and mitigation strategies to cope with loss of large area accident due to explosion and fire

Designed to take into account potential impact of a large, commercial aircraft
crash, accordance with 10 CFR 50.150 & regulatory Guide 1.217

Tsunami Barrier

Tsunami Barrier

Waterproof Door

Waterproof Door

Advanced
Technology
Fully Digitalized I&C System with Diverse Platforms

Independent & diverse actuation system provided to cope with software Common Cause Failures(CCFs) of the safety-related I&C systems

Fully digitalized Man-Machine Interface System(MMIS) installed in Main Control Room(MCR)

  • Allows operators focus on their work in a user friendly & unobstructed way which enhances the reliability of plant operation
MMIS / Main Control Room

MMIS / Main Control Room

Seismic Analysis Enveloping Multiple Sites

Has capacity to deal with wide range of site-specific parameters

  • ex. Site shear wave velocity profiles, ambient temperatures, wind speeds

Hard rock high frequency response spectra covers approx. 80% of ground motion response spectra of central/eastern US NPP sites

Radiation Protection Design

Ensures the radiation exposure to workers and public during normal plant operations & postulated accident conditions within the regulatory limit & maintained As Low As Reasonably Achievable(ALARA)

  • Achieved by the use of low corrosive materials, RCS chemistry control, high fuel performance, the treatment of radioactive materials, the monitoring of releases, provision of sufficient radiation shielding and prevention, the detection and collection of contamination
Minimization of Contamination/ Radwaste Generation

Minimize the Use of Embedded and Buried Piping, Provides Leak Detection Instrumentation, Drainage Trenches, Double-Walled Piping for All Radioactive and Potentially Radioactive Systems

Comply with Design Requirements of 10 CFR 20.1406 & Regulatory Guide 4.21

Excellence in Construction
Equipment Modularization

Pre-fabrication of modules helps the reduction of field work & on-site labor congestion

  • Approximately 80 items selected for modularization
  • Modules can be lifted & installed using a large capacity crane

Representatively, the internal components of the reactor are fabricated in two parts

  • Integrating instead of the use of on-site Welding
Modularized Reactor Internals

Modularized Reactor Internals

Top-Down Method

Use the top-down method with large capacity cranes to reduce the construction period

3D Design Method

Prevents errors & results in reduced construction costs

Allow engineers enhance constructability & maintainability of the plant

  • By utilizing various design output such as drawing & a list of materials through the verified 3D CAD Model
3D Modelling Images

3D Modelling Images

Outstanding
Performance
60 Years of Lifetime with Availability over 90%
Convenient Operation & Maintenance

Independent & diverse actuation system provided to cope with software Common Cause Failures(CCFs) of the safety-related I&C systemsRemovable shield blocks & covers lower the radiation level to allow personal access to the containment during power operation

Integrated Head Assembly(IHA) & permanent refueling pool seal simplify refueling works

High Performance Fuel Assembly

Utilize Plus 7TM, An Advanced Fuel Assembly with High Thermal Performance etc.

A High Burnup Capability of 55 GWD/MTU(batch Average)

More than 5,000 Plus7TM Fuel Assemblies Have Been Commercially Supplied & Operated in NPPs as of 2017

Integrated Head Assembly

Integrated Head Assembly

Easy Removable Intergated Top Nozzle, Reduced Rod Bow Inconel Top Grid, High Seismic And Fretting Wear Resistant ZIRLO Mid Grid, High Bum-Up Inconel Bottom Grid, Debirs Filtering Bottom Nozzle

PLUS 7

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