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APR1400: Evolutionary Korean Next Generation Reactor

[+] Author Affiliations
Insik Kim, Dong-Su Kim

Korea Power Engineering Company, Inc., Daejeon, Korea

Paper No. ICONE10-22441, pp. 845-851; 7 pages
doi:10.1115/ICONE10-22441
From:
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 2
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3596-0 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME

abstract

Following the Korean Standard Nuclear Power Plant (KSNP) program which has shown its success through operation of its first units, Ulchin 3&4, Korean nuclear industry, with the support of Korean government, has launched its next program to develop 4000MWt (1400MWe) Advanced Power Reactor, APR1400, as a Korean next generation reactor. It is to complete an advanced standardized plant design, with increased power and with higher confidence in safety, performance, construction and operation as well as economics relative to the currently operating KSNPs. Three-phase development program was ended in December 2001, and it is our next task to implement the developed design in actual construction and to proceed commercial operation. The key to the APR1400 design development is an evolutionary approach that relies on use of proven KSNP design concepts and proven components to get high confidence in design itself and thus to make use of earned credits in safety and performance. Furthermore, advanced features and design improvements are implemented to provide additional benefits. These features are to provide additional thermal margins; to better accommodate transients and reduce unnecessary challenges to the plant safety system; to mitigate severe accident conditions; to simplify structures and to improve operability. This paper describes the development approach of the APR1400, and introduces major design features including design improvements and advanced design features focusing on the nuclear steam supply system (NSSS).

Copyright © 2002 by ASME

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