Integral Effect Tests on Transient Thermal-Hydraulic Behavior during a Steam Generator Tube Rupture Accident in the APR1400

Kang, Kyoung-Ho; Park, Hyun-Sik; Cho, Seok; Choi, Nam-Hyun; Chu, In-Cheol; Yun, Byong-Jo; Kim, Kyungdoo; Kim, Yeon-Sik; Baek, Won-Pil; Choi, Ki-Yong

doi:10.13182/nt12-a13482

Cited by 4 publications

(1 citation statement)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A typical measured primary pressure for a single U-tube rupture is shown in Figure 25. In this figure, AFAS stands for Auxiliary Feedwater Actuation Signal and it implies that auxiliary feedwater was provided into the intact steam generator between 3153 s and 3911 s. More information can be found in the literature [25]. The typical sequence of events was experimentally identified.…”

Section: Steam Generator Tube Rupture (Sgtr)mentioning

confidence: 99%

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Choi

Kim

Song

et al. 2012

Science and Technology of Nuclear Installations

Self Cite

View full text Add to dashboard Cite

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 R&D program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

show abstract

Section: Steam Generator Tube Rupture (Sgtr)mentioning

confidence: 99%