Advanced Power Reactor 1400
The Advanced Power Reactor 1400 ( APR-1400 ) is a South Korean pressurized water reactor type that replaces the previous standard type OPR-1000 . The reactor is designed for a thermal output of 4000 MW with an electrical output of 1455 MW ( efficiency of 36%). It is considered to be an advanced generation III type of NPP.
technical features
The APR-1400 is based on the American Design System 80 from Combustion Engineering . The design process began in 1992/94 as the Korean Next Generation Reactor at Korea Hydro & Nuclear Power .
The reactor core consists of 241 fuel elements , 93 control rods and 61 measuring rods. The fuel ( uranium dioxide ) is enriched to an average of 2.6% . Up to 30% of the core can also be loaded with MOX fuel elements . The burn-up is up to 55 GWd / t fuel. The APR-1400 reactors are designed for 60 years.
The two cooling circuits are designed redundantly. The steam generators , each with 13,102 tubes, are made of the Inconel 690 alloy and include feed water preheaters .
Locations
Two units of this type are currently in operation at the Kori nuclear power plant in South Korea and two additional units (Shin-Kori 5 and 6) are under construction, as are the two at the Hanul nuclear power plant (Shin-Hanul-1 and -2). In the United Arab Emirates another 4 units are being built at the Barakah nuclear power plant .
See also
literature
- Sang-Seob Lee, Sung-Hwan Kim, Kune-Yull Suh: THE DESIGN FEATURES OF THE ADVANCED POWER REACTOR 1400 . In: Nuclear Engineering and Technology . tape 41 , no. 8 , January 1, 2009, doi : 10.5516 / NET.2009.41.8.995 ( kns.org [PDF]).
- World Nuclear Association: Advanced Nuclear Power Reactors
Individual evidence
- ^ World Nuclear
- ^ Paul Laufs: Reactor Safety for Power Nuclear Power Plants . Springer-Verlag, 2013, ISBN 978-3-642-30655-6 , pp. 968 ( limited preview in Google Book search).
- ↑ PRIS. International Atomic Energy Agency , January 14, 2020, accessed on January 14, 2020 .