Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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INTEGRAL BEHAVIOR OF THE ATLAS FACILITY FOR A 3-INCH SMALL BREAK LOSS OF COOLANT ACCIDENT

  • Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Cho, Seok (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Euh, Dong-Jin (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Yeon-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Baek, Won-Pil (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
  • Published : 2008.04.30
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Abstract

A small-break loss of coolant accident (SB-LOCA) test with a break size equivalent to a 3-inch cold leg break of the APR1400 was carried out as the first transient integral effect test using the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation). This was the first integral effect test to investigate the integral performance of the test facility and to verify its simulation capability for one of the design-basis accidents. Reasonably good thermal hydraulic data was obtained so that an integral performance of the fluid sub-systems was identified and control performance of the ATLAS was confirmed under real thermal hydraulic conditions. Based on the measured data, a post-test calculation was carried out using the best-estimate thermal hydraulic safety analysis code, MARS 3.1, and the similarity between the expected and actual data was investigated. On the whole, the post-test calculation reasonably predicts the major thermal hydraulic parameters measured during the SB-LOCA test. The obtained data will be used to enhance the simulation capability of the ATLAS and to improve an input model of the ATLAS for simulation of other target scenarios.

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References

  1. S. K. Moon, C.-H. Song, C. K. Park, T. S. Kwon, B. J. Yun and M. K. Chung, 'A state-of-the-Art Report on the Study of the Nuclear Reactor Thermal Hydraulics Using Integral Test Facilities,' KAERI/AR-509/98 (1998)
  2. Y. S. Kim, B. U. Bae, and G. C. Park, 'Integral Loop Test and Assessment of Modified RELAP5/MOD3.3 for RCS Coolant Inventory during a LBLOCA,' Nuclear Engineering and Design, 237, 182 (2007) https://doi.org/10.1016/j.nucengdes.2006.05.010
  3. B. U. Bae, K. H. Lee, and G. C. Park, 'Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400,' ICAPP '07, Nice, France, May 13-18 (2007)
  4. W. P. Baek, C.-H. Song, B. J. Yun, T. S. Kwon, S. K. Moon and S. J. Lee, 'KAERI Integral Effect Test Program and the ATLAS Design,' Nucl. Technol., 152, 183 (2005) https://doi.org/10.13182/NT05-A3669
  5. K. Y. Choi, H. S. Park, D. J. Euh, T. S. Kwon, and W. P. Baek, 'Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents,' Nucl. Technol., 156, 256 (2006) https://doi.org/10.13182/NT06-A3789
  6. I. C. Chu, C.-H. Song, B. H. Cho and J. K. Park, 'Development of Passive Flow Controlling Safety Injection Tank for APR1400,' Nuclear Engineering and Design, 238, 200 (2007) https://doi.org/10.1016/j.nucengdes.2007.07.002
  7. Y. S. Kim, W. P. Baek, C.-H. Song, K. Y. Choi, H. S. Park, S. Cho, K. H. Kang, B. D. Kim, S. K. Moon, B. J. Yun, C. H. Chung, T. S. Kwon, D. J. Euh, N. H. Choi, J. K. Park, and K. H. Min, 'Startup Test Report of ATLAS,' KAERI/ TR-3330/2007 (2007)
  8. 'MARS Code Manual Volume I: Code Structure, System Models, and Solution Methods,' KAERI/TR-2812/2004 (2004)
  9. M. Ishii and I. Kataoka, 'Similarity Analysis and Scaling Criteria for LWRs Under Single Phase and Two-Phase Natural Circulation,' NUREG/CR-3267, ANL-83-32, Argonne National Laboratory (1983)
  10. H. S. Park, S. K. Moon, B. J. Yun, T. S. Kwon, K. Y. Choi, C. K. Park, S. Cho, S. D. Hong, S. J. Yi, Y. S. Kim, C.-H. Song, and W. P. Baek, 'Calculation Sheet for the Basic Design of the ATLAS Fluid System,' KAERI/TR-3333/ 2007 (2007)
  11. K. Y. Choi, T. S. Kwon, S. Cho, H. S. Park, J. T. Kim and W. P. Baek, 'Control and Data Acquisition System of the ATLAS Facility,' KAERI/TR-3338/2007 (2007)
  12. INEL, 'RELAP5/MOD3.2.1 Code Manual,' USNRC Report, NUREG/CR-5535 (1998)
  13. M.J. Thurgood and M. J. George, 'COBRA/TRAC: A Thermal-hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems,' USNRC Report, NUREG/CR-3046 (1983)
  14. B. J. Yun, D. J. Euh, K. H. Kang, C.-H. Song, and W. P. Baek, 'Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow,' The 11th Int. Topical Meeting on Nuclear Reactor Thermal- Hydraulics (NURETH-11), Avignon, France, October 2-6 (2005)