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Science and Technology of Nuclear InstallationsVolume 2012 2012, Article ID 375070, 18 pages

Research ArticleKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of Korea

Received 15 August 2011; Accepted 12 November 2011

Academic Editor: Klaus Umminger

Copyright © 2012 Ki-Yong Choi et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


A large-scale thermal-hydraulic integral effect test facility, ATLAS Advanced Thermal-hydraulic Test Loop for Accident Simulation, has been operated by KAERI. The reference plant of ATLAS is the APR1400 Advanced Power Reactor, 1400 MWe. Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line break tests, and steam line break tests. These tests contributed toward an understanding of the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing validation data for evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Major discoveries and lessons found in the past integral effect tests are summarized in this paper. As the demand for integral effect tests is on the rise due to the active national nuclear RandD program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

Autor: Ki-Yong Choi, Yeon-Sik Kim, Chul-Hwa Song, and Won-Pil Baek



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