KEPCO E&C is preparing to take a new leap forward in the Gimcheon new office building.

APR1400

APR1400

APR1400 picture

APR1400 is a next-generation type nuclear power plant developed by improving OPR1000, which is the Korea’s major power plant model. It was developed through the government-led G-7 Project from December 1992 to December 2001. KEPCO E&C was in charge of technology development in A/E and NSSSD.

APR1400 is a cutting-edge nuclear power plant, which has raised the generating capacity from 1000MW to 1400MW, and design lifetime has been increased from 40 years to 60 years. It has received evaluation having the advantages beyond the technological levels of Generation III nuclear power plants developed by nuclear advanced countries. In particular, regarding safety aspect, it boasts the world’s top class. To strengthen safety, APR1400, in its standard design reflected design to cope with earthquake to satisfy all the 0.3g seismic requirements in the bedrock and soil conditions according to site envelope concept. In addition, by introducing quadrant layout design method of auxiliary building, the ability to cope with external shock such as fire, flood, and earthquake, was strengthened a step further.

APR1400 was first applied in building Shin-Kori Nuclear Power Plant Units 3 & 4 in August 2006, and afterwards, total of 6 plants – Shin-Hanul Units 1 & 2, Shin-Kori Units 5 & 6, and Shin-Hanul Units 3 & 4 – are being constructed. In particular, in 2009, it is applied to UAE BNPP Units 1–4, the first export model of Korean nuclear power plant, and is currently being constructed.

Meanwhile, with the successful exportation of APR1400 to UAE, to strengthen international status and competitiveness even more, KEPCO E&C, KEPCO, and Korea Hydro & Nuclear Power (KHNP) signed a joint agreement, and are trying to obtain Design Certification (DC) from Nuclear Regulatory Commission (NRC) of the U.S.A. Design Certification (DC) is a system to obtain certification for safety in advance from the regulatory agency regarding the standard design of certain reactor types. In March 2015, it has passed the preliminary review of the Design Certification(DC) from Nuclear Regulatory Commission (NRC) and is now being reviewed. After the review is finished and safety evaluation procedure is completed by September 2018, public hearing and deliberation process will be followed, and we are expecting to obtain Design Certification (DC) in May 2019. After the APR1400 Design Certification (DC) is completed, the exportation competitiveness in the foreign market including the U.S.A. will be enhanced and the exportation of the follow-up nuclear plant to the UAE nuclear power plants will become more active.

Major Design Characteristics

APR1400 Schematic Diagram
Features
  • TypePressurized Water Reactor
  • Capacity1,400MW class (4,000MWt)
  • Design Lifetime60 Years
  • Seismic Design StandardSSE 0.3g
Performance
  • AvailabilityAverage of 90% or Higher
  • Unplanned Trip0.8 Time/Year or Less
  • Refueling Interval18 Months
  • Load Rejection Capability Maintain House Load in 100% Load Rejection
Safety
  • Core Damage Frequency10 /RY
  • Containment Failure Frequency10 /RY or Less
  • Occupational Radiation Exposure Dose1man-㏜/RY or Less
  • Thermal Margin10% or higher
  • Station Blackout Coping Time8 Hours Minimum
  • Containment BuildingPS Concrete Structure

Design and Operation Data

  • Nuclear Steam Supply System
    Number of Coolant Loops
    2
    Primary Circuit Volume, including Pressurizer
    334.9㎥
    Steam Flow Rate at Normal Conditions
    5,769,695㎏/hr
  • Reactor Coolant System
    Primary Coolant System Flow Rate
    1,689㎥/min
    Operating Pressure
    158.2㎏/㎠
    Coolant Inlet Temperature at RV Inlet
    290.6℃
    Coolant outlet Temperature at RV Outlet
    323.9℃
  • Reactor Core
    Active Core Height
    381㎝
    Equivalent Core Diameter
    365㎝
    Average Linear Heat Rate
    17.92㎾/m
    Number of Fuel Assemblies
    211
    Number of Control Element Assemblies
    18months
    Operating Cycle Length(Full Cycle Length)
    93
  • Reactor Pressure Vessel
    Cylindrical Shell Inner Diameter
    462.92cm
    Wall Thickness of Cylindrical Shell
    23.0cm minimum
    Total Height
    1,463cm
  • Steam Generator
    Type
    Vertical U-Tube with Integral Economizer
    Heat Transfer Surface Area
    9,522.6㎡
    Primary/Secondary Operating Pressure
    158.2/75.2㎏/㎠
    Maximum Moisture Content at SG
    0.25% or Less
  • Reactor Coolant Pump
    Type
    Single Stage, Centrifugal, Vertical
    Rated Flow Rate
    461.3㎥/min
    Rated Pump Head
    109.7m
    Pump Speed
    1,190rpm
  • Pressurizer
    Total Volume
    68.9㎥
    Steam Volume (Full Power)
    34.9㎥
    Design Temperature / Pressure
    371℃/175.8㎏/㎠
    Heating Power of the Heater Rods
    2,400㎾
  • Containment Building
    Type
    Prestressed Cylindrical Concrete with Steel Liner
    Inside Diameter
    45.7m
    Height
    76.4m
    Normal Operating Temperature
    48.9℃
  • Turbine
    Type
    6-Flow, Tandem-Compound, 52"LSB
    Speed
    1,800rrpm
  • Generator
    Type
    Synchronous, 4 Poles
    Voltage
    24㎸, 3 Phases
    Frequency
    60㎐