The APR-1400 (for Advanced Power Reactor 1400 MW electricity) is an advanced pressurized water nuclear reactor designed by the Korea Electric Power Corporation (KEPCO). Originally known as the Korean Next Generation Reactor (KNGR), this Generation III reactor was developed from the earlier OPR-1000 design and also incorporates features from the US Combustion Engineering (C-E) System 80+ design. Currently in South Korea there are 4 units in operation (Saeul unit 1 and 2, formerly known as Shin Kori unit 3 and 4, Shin Hanul units 1 and 2), and 2 units in construction (Saeul unit 3 and 4, formerly Shin Kori unit 5 and 6). Four units are completed and in commercial operation in the United Arab Emirates at Barakah.
History
APR-1400 design began in 1992 and was awarded certification by the Korean Institute of Nuclear Safety in May 2002. The design certification application was submitted to the US Nuclear Regulatory Commission (NRC) in December 2014 and in March 2015, it was accepted for technical review to determine if the reactor design meets basic US safety requirements.
In October 2017, European Utility Requirements (EUR) organization approved changes to the APR-1400 design for emergency cooling, allowing the design to be built in countries outside Europe to EUR certification.
As of September 2018, the NRC issued its final safety evaluation report and standard design approvalBrown, Frederick D. (28 September 2018). "Standard Design Approval for the Advanced Power Reactor 1400" (PDF) (Letter). Letter to Mr. Yun-Ho Kim. Retrieved 14 May 2019. finding the design technically acceptable and valid for 15 years. In April 2019, the NRC approved a rule to certify the APR-1400 standard design. In September 2018, the U.S. Nuclear Regulatory Commission gave the APR-1400 Standard Design Approval, and in September 2019 it received a design certificate valid for 15 years.
In 2022, Westinghouse Electric Company, which had acquired Combustion Engineering in 2000, filed a lawsuit in a U.S. federal court against KHNP and Kepco alleging that the APR-1400 was copied from the System 80 reactor. This had the indirect effect that the U.S. government rejected a request for necessary APR-1400 permission to export to a third country while the case is resolved.
Locations
South Korea The first commercial APR-1400 reactors at Shin Kori were approved in September 2007, with construction starting in October 2008 (Unit 3) and August 2009 (Unit 4). Shin Kori-3 was initially scheduled to commence operation by the end of 2013, but the schedules for both Units 3 & 4 were delayed by approximately one year to replace safety-related control cabling, which had failed some tests. Construction of two more APR-1400 units at Shin Kori, Korea (Units 5 and 6) had been expected to begin in 2014, but as of December 2016 plans had not been finalised.
Construction of two new APR-1400s, Shin Hanul Units 1 & 2, began in May 2012 (Unit 1) and June 2013 (Unit 2), with Unit 1 expected to be completed in April 2017. Two more APR-1400s at Shin Hanul were approved in 2014, with construction to start in 2017.
After the election of President Moon Jae-in in May 2017, Korea Hydro & Nuclear Power (KHNP) suspended design work on Shin Hanul-3 and -4, and construction work was suspended on Shin Kori-5 and -6 in July 2017 for a three-month period while a government-appointed committee met to discuss the country's future nuclear power policy. President Moon had signed an agreement in March 2017 calling for the phase-out of nuclear energy while campaigning for president. In October 2017, the committee recommended proceeding with the construction of Shin Kori-5 and -6. President Moon announced he supported the committee's decision, but added that no new construction would be allowed, throwing doubt on the fate of Shin Hanul-3 and -4.
As of April 2020, Shin-Kori 1 and 2 and Shin-Hanul 1 are operational while Shin-Hanul 2 being loaded with fuel.
United Arab Emirates In December 2009, a KEPCO-led consortium was awarded the contract to build four APR-1400 reactors at Barakah, United Arab Emirates. Construction of Barakah Unit 1 started in July 2012, Unit 2 started construction in May 2013, Unit 3 started construction in September 2014 and Unit 4 started construction in September 2015. Block 1 started to produce energy on 1 August 2020 and went into commercial operation on 6 April 2021."Arabische Emirate nehmen erstes AKW in Betrieb", Deutsche Welle. 1 August 2020. Retrieved 2 August 2020. several research projects were performed at Khalifa University to ensure the safe operation for the APR1400 nuclear power plant. On 5 September 2024, the fourth and final reactor started commercial production.
United Kingdom NuGeneration (NuGen) was formed as the joint venture between Engie, Iberdrola, and Scottish and Southern Energy (SSE) to develop the Moorside Nuclear Power Station in Cumbria; the initial plans called for three Westinghouse AP1000 units. SSE was bought out by Engie and Iberdrola in 2011, and Iberdrola's share, in turn, was purchased by Toshiba in 2013. Following the bankruptcy of Toshiba's subsidiary Westinghouse Electric Corporation in March 2017, Engie pulled out of NuGen in July, leaving Toshiba as the sole owner of NuGen. In December 2017, NuGen announced that KEPCO was named the preferred bidder to acquire NuGen from Toshiba; the three AP1000 reactors were to be replaced by two APR-1400 units. In July 2018 Kepco's preferred bidder status was terminated, in response to difficulties financing the development.
Poland In October 2022, Polish utilities PGE and ZE PAK announced an agreement with KHNP to build a number of APR-1400 reactors near ZE PAK's coal-fired plant at Pątnów. In 2025, Korea Hydro & Nuclear Power withdrew from the deal.
Czech Republic In 2024 KHNP was selected to supply 2 of APR-1000 reactors (France's EDF with EPR1200 type of reactor was the other bidder). The expected date for the unit for test operation is 2036 and commercial operation in 2038. In May 2025 French EDF appealed the decision to award the contract to KHNP, the court ordered temporarily to stop the contract (construction hasn't yet started).
On 4 June 2025 the contract with KHNP for 2 units of APR-1000 was signed after the court has lifted injunction. Local Czech companies will take 60% of construction work. The price of electricity will be under 90 euros per megawatt hour (cheaper than from similar nuclear reactors in UK and Poland).
The total cost of 2 APR-1000 units is projected to be $18.6 billion (CZK407 billion) including the first fuel batch. Construction is expected to start in 2029.
Summary + APR-1400 SummaryPower plantsReactorsStatusConstructionOperation StartUnitCountryModelStartCompleteSaeul 1 South KoreaAPR-1400 16 October 2008 30 October 2015 12 December 2016 Saeul 2 South KoreaAPR-1400 19 August 2009 November 2015 August 2019 Saeul 3 South KoreaAPR-1400 September 2016 12 April 2026 August 2026 Saeul 4 South KoreaAPR-1400 September 2017 – November 2026Shin-Hanul 1 South KoreaAPR-1400 10 July 2012 May 2022 Shin-Hanul 2 South KoreaAPR-1400 19 June 2013 April 2020 December 2023 Shin-Hanul 3 South KoreaAPR-1400 May 2025 2032 (est) 2032 (est) Shin-Hanul 4 South KoreaAPR-1400 29 May 2026 2033 (est) 2033 (est) Barakah 1 United Arab EmiratesAPR-1400 18 July 2012 5 May 2017 6 April 2021 Barakah 2 United Arab EmiratesAPR-1400 28 May 2013 24 March 2022 Barakah 3 United Arab EmiratesAPR-1400 24 September 2014 4 November 2021 24 February 2023 Barakah 4 United Arab EmiratesAPR-1400 2 September 2015 – 5 September 2024Dukovany 5Czech RepublicAPR-1000PlannedDukovany 6Czech RepublicAPR-1000Planned
Notes
Design The APR-1400 is an evolutionary Advanced Light Water Reactor which is based on the previous OPR-1000 design. Under Korean conditions, the reactor produced 1455 MW gross electrical power with a thermal power capacity of 3983 MW (4000 MW nominal).
The design was developed to meet 43 design requirements, with the main developments being evolution in capacity, increased lifetime and enhanced safety. The design improvements also focus on meeting economic objectives and licensing requirements. Compared to the OPR-1000, the key features are:
Net Electric power: 1400 MW (40% increase) Design Life: 60 years (50% increase) Seismic Design Basis: 0.3g (50% increase) Core Damage Frequency: less than 10−5/yr (10x decrease) Core fuel assemblies: 241 (36% increase)
Several other changes were incorporated such as moving to complete digital I/C and implementation of new systems in the Safety Injection System (SIT).
Core The reactor core of the APR-1400 consists of 241 fuel assemblies, 93 control element assemblies, and 61 in-core instrumentation assemblies. Each fuel assembly has 236 fuel rods in a 16 x 16 array (some space is taken up by guide tubes for control elements) containing Uranium dioxide (average enrichment of 2.6 w/o),Alrwashdeh, Mohammad, and Saeed A. Alameri. 2022. "SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis" Energies 15, no. 10: 3772. https://doi.org/10.3390/en15103772Alaleeli, Maithah M., Saeed A. Alameri, and Mohammad Alrwashdeh. 2022. "Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions" Energies 15, no. 14: 5204. https://doi.org/10.3390/en15145204Alrwashdeh, Mohammad, and Saeed A. Alameri. 2022. "Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core" Energies 15, no. 21: 8008. https://doi.org/10.3390/en15218008Alrwashdeh, Mohammad, and Saeed A. Alameri. "Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly." Nuclear Engineering and Design 384 (2021): 111486. which is capable of producing an average volumetric power density of 100.9 W/cm^3. Up to 30% of the core can also be loaded with Mixed Oxide fuel with minor modifications. The core is designed for an 18-month operating cycle with a discharge burnup up to 60,000 MWD/MTU, with a thermal margin of 10%. For the control element assemblies, 76 Boron carbide pellets rods are used in the full strength control rods, while 17 Inconel-625 is used in the part strength control rods.
Primary Like the OPR-1000 and preceding C-E designs, the APR-1400 has two reactor coolant loops. In each loop, heated primary coolant leaves the reactor pressure vessel (RPV) through one hot leg, passing through one steam generator (SG), returning to the reactor vessel through two cold legs, each equipped with a reactor coolant pump (RCP). In loop 2, there is one pressurizer (PZR) on the hot leg, where a steam bubble is maintained during operation. The loops are arranged symmetrically, so the hot legs are diametrically opposed on the RPV's circumference. Because the steam generators are elevated relative to the RPV, natural convection will circulate reactor coolant in the event of RCP malfunction. The pressurizer is equipped with a pilot-operated relief valve which not only protects against Reactor Coolant System over-pressure, it also allows manual depressurization in the case of a total loss of feedwater.
Secondary