KEPCO E&C

APR1400

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 export of APR1400 to UAE, to strengthen international status and competitiveness even more, KEPCO E&C and Korea Hydro & Nuclear Power (KHNP) signed a joint agreement, and in November 2017, obtained the European Utility Requirements(EUR) Certification of EU-APR that is an evolutionary Advanced Light Water Reactor fully complying with the EU requirements and European codes & standards. Also, with the joint agreement with KEPCO and KHNP, KEPCO E&C was able to aequire Design Certification(DC) of APR1400 from Nuclear Regulatory Commission (NRC) of the U.S.A. in August 2019. 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. With the EUR Certification of EU-APR and NRC Design Certification of APR1400, the export competitiveness in the foreign market including U.S.A., Poland, and Egypt will be enhanced, and the additional export of nuclear power plants along with those of UAE is expected.

Major Design Characteristics

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 Frequency1.0x10^-5/RY or Less
• Containment Failure Frequency1.0x10^-6/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