Technology
By undertaking nuclear power plant projects constantly, TEAM KOREA has maintained an edge in the global nuclear industry – in both technology and experience.
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 2이9.
By achieving NRC approval - the international "Gold Standard - for design and safety - the APR1400 brings improved public confidence and internationalreputation.
GENERAL PLANT DATA
| 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
| 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
| REACTOR COOLANT SYSTEM | Number of Loops | 2 |
|---|---|---|
| Operating Pressure | 15.5 Mpa | |
| Inlet Temperature | 290.6℃ | |
| Outlet Temperature | 323.9℃ |
Enhanced Safety
- 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)
- 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, SDVS
Rapidly 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
- Safety Depressurization & Vent System, SDVS
- 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
Advanced Technology
- 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
- 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
- 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
- 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
- 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
- Use the top-down method with large capacity cranes to reduce the construction period
- 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
Outstanding Performance
- Removable 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
- 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
