Full Content is available to subscribers

Subscribe/Learn More  >

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
  • 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


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



Interactive Graphics


Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In