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http://dx.doi.org/10.5516/NET.2009.41.6.775

LBLOCA AND DVI LINE BREAK TESTS WITH THE ATLAS INTEGRAL FACILITY  

Baek, Won-Pil (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Kim, Yeon-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.41, no.6, 2009 , pp. 775-784 More about this Journal
Abstract
This paper summarizes the tests performed in the ATLAS facility during its first two years of operation (2007${\sim}$2008). Two categories of tests have been performed successfully: (a) the reflood phase of the large-break loss-of-coolant accidents in a cold leg, and (b) the breaks in one of four direct vessel injection lines. Those tests contributed to understanding the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing an evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Several important and interesting phenomena have been observed during the tests. In most cases, the ATLAS shows reasonable accident characteristics and conservative results compared with those predicted by one-dimensional safety analysis codes. A wide variety of small-break LOCA tests will be performed in 2009.
Keywords
ATLAS; APR1400; OPR1000; Direct Vessel Injection; Integral Effect Test;
Citations & Related Records

Times Cited By Web Of Science : 8  (Related Records In Web of Science)
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1 Lee, B.R. et al. (1992), “Korean Standard Nuclear Power Plant: Safer, Simpler, Easier to Build,” Nucl. Eng. Int., Aug. (1992)
2 OECD/NEA (2007), Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR), Report No. NEA/CSNI/R(2007)6
3 Yun, B.J. et al. (2003), “Experimental Observations of the Hydraulic Phenomena in the APR1400 Downcomer during the DVI Line Break Accident,” Proc. of KNS Spring Mtg, Gyeongju, Korea, May 2000
4 Baek, W.P. and Kim, Y.S. (2008). 'Accident Simulation ATLAS for APWRs,' Nucl. Eng. Int., 53(646), pp. 21-25
5 EPRI (1995), “EPRI Utility Requirement Documents for the Advanced Light Water Reactor (Chapter 5).”
6 Song, C.H. et al. (2000), “Thermal Hydraulic Test Program for Evaluating or Verifying the Performance of New Design Features in KNGR,” Proc. of KNS Autumn Mtg., Daejeon, Korea, Oct. 2000
7 Kim, Y.S. et al. (2008). “Commissioning of the ATLAS Thermal-Hydraulic Integral Test Facility,” Ann. Nuc. Energy., 35(10), pp. 1791-1799   DOI   ScienceOn
8 Bae, B. U. et al. (2007), “Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400,” Proc. of ICAPP 2007, Nice, France, May 13-18, 2007
9 Choi, K.Y. et al. (2005). “Simulation Capability of the ATLAS Facility for Major Design Basis Accidents,” Nucl. Technol., 156(3), pp. 199-212
10 Choi, K.Y. et al. (2009), ISP-50 Specifications for a Direct Vessel Injection Line Break Test with the ATLAS, Report No. KAERI/TR-3778/2009, Korea Atomic Energy Research Institute
11 Park, H.S. et al. (2008), “Overview of the KAERI LBLOCA Reflood Test Program Using the ATLAS Facility,” Proc. of the NUTHOS-7, Seoul, Korea, October 5-9, 2008
12 Ishii, M. and Kataoka, I. (1983), “Similarity Analysis and Scaling Criteria for LWRs Under Single Phase and Two- Phase Natural Circulation,” NUREG/CR-3267, ANL-83-32, Argonne National Laboratory
13 Kim, I. and Kim, D.S. (2002), “APR1400: Evolutionary Korean Next Generation Reactor,” Proc. 10th Int. Conf. on Nuclear Engineering (ICONE-10), Arlington, Virginia, US, 14-18 April 2002   DOI
14 Baek, W.P. et al. (2005). “KAERI Integral Effect Test Program and the ATLAS Design,” Nucl. Technol., 152(2), pp. 183-195