Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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FIRST ATLAS DOMESTIC STANDARD PROBLEM (DSP-01) FOR THE CODE ASSESSMENT

  • Received : 2010.10.28
  • Accepted : 2010.12.24
  • Published : 2011.02.25
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Abstract

KAERI has been operating an integral effect test facility, ATLAS (Advanced Thermal-Hydraulic Test Loop for Accident Simulation), for accident simulations of advanced PWRs. Regarding integral effect tests, a database for major design basis accidents has been accumulated and a Domestic Standard Problem (DSP) exercise using the ATLAS has been proposed and successfully performed. The ATLAS DSP aims at the effective utilization of an integral effect database obtained from the ATLAS, the establishment of a cooperative framework in the domestic nuclear industry, better understanding of thermal hydraulic phenomena, and an investigation of the potential limitations of the existing best-estimate safety analysis codes. For the first ATLAS DSP exercise (DSP-01), integral effect test data for a 100% DVI line break accident of the APR1400 was selected by considering its technical importance and by incorporating comments from participants. Twelve domestic organizations joined in this DSP-01 exercise. Finally, ten of these organizations submitted their calculation results. This ATLAS DSP-01 exercise progressed as an open calculation; the integral effect test data was delivered to the participants prior to the code calculations. The MARS-KS was favored by most participants but the RELAP5/MOD3.3 code was also used by a few participants. This paper presents all the information of the DSP-01 exercise as well as the comparison results between the calculations and the test data. Lessons learned from the first DSP-01 are presented and recommendations for code users as well as for developers are suggested.

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References

  1. 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).
  2. K. Y. Choi et al, “Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents,” Nuclear Technology, 156, 256 (2006).
  3. W. P. Baek and Y. S. Kim, “Accident Simulation ATLAS for APWRs,” Nuclear Engineering International, 53, 21 (2008).
  4. Y. S. Kim et al, “Commissioning of the ATLAS Thermal-Hydraulic Integral Test Facility,” Annals of Nuclear Energy, 35, 1791 (2008). https://doi.org/10.1016/j.anucene.2008.05.010
  5. K. Y. Choi et al., “Experimental Simulation of a Direct Vessel Injection Line Break of the APR1400 with the ATLAS,” Nuclear Engineering and Technology, 41, 655 (2009). https://doi.org/10.5516/NET.2009.41.5.655
  6. K.Y. Choi, et al., “Comparison Report of Open Calculations for ATLAS Domestic Standard Problem (DSP-01),” KAERI/TR-4073/2010, Korea Atomic Energy Research Institute (2010).
  7. K. Y. Choi, et al., “Integral Behavior of the ATLAS Facility for a 3-inch Small Break Loss of Coolant Accident,” Nuclear Engineering and Technology, 40, 199 (2008). https://doi.org/10.5516/NET.2008.40.3.199
  8. W. P. Baek et al., “LBLOCA and DVI Line Break Tests with the ATLAS Integral Facility,” Nuclear Engineering and Technology, 41, 775 (2009). https://doi.org/10.5516/NET.2009.41.6.775
  9. S. Cho et al., “Core Thermal Hydraulic Behavior During the Reflood Phase of Cold-leg LBLOCA Experiments using the ATLAS Test Facility,” Nuclear Engineering and Technology, 41, 1263 (2009). https://doi.org/10.5516/NET.2009.41.10.1263
  10. H. S. Park et al., “An Integral Effect Test on the LBLOCA Reflood Phenomena for the APR1400 using the ATLAS under a Best-Estimate Condition,” J. of Nuclear Science and Technology, 46, 1059 (2009). https://doi.org/10.3327/jnst.46.1059
  11. K.Y. Choi et al., “Double-Ended Break Test of an 8.5 inch Direct Vessel Injection Line Using the ATLAS,” KAERI/TR-3990/2010, Korea Atomic Energy Research Institute (2010).
  12. K. H. Kang, et al, “ATLAS Facility and Instrumentation Description Report,” KARE/TR-3779/2009, Korea Atomic Energy Research Institute (2009).
  13. The American Society of Mechanical Engineers, “Test Uncertainty,” ASME PTC 19.1-1998 (1998).
  14. B. J. Yun et al., “Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow,” The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2 - 6 (2005).
  15. Ambrosini W., Bovalini R., D'Auria F., "Evaluation of Accuracy of Thermal Hydraulic Code Calculations", J. Energia Nucleare, Vol. 2, (1990).
  16. D'Auria, F., Leonardi, M., Pochard, R., “Methodology for the Evaluation of Thermal Hydraulic Codes Accuracy,” Proc. Int. Conf. on New trends in Nuclear System Thermohydraulics, Pisa, 467–477 (1994).
  17. Robert F. Kunz, Gerald F. Kasmala, John H. Mahaffy, Christopher J. Murray, “On the Automated Assessment of Nuclear Reactor Systems Code Accuracy,” Nuclear Engineering and Design, Vol. 211, Issues 2-3, 245-272, (2002). https://doi.org/10.1016/S0029-5493(01)00440-X
  18. Andrej Prosek, Francesco D'Auria, David J. Richards, Borut Mavko, ”Quantitative Assessment of Thermal-Hydraulic Codes Used for Heavy Water Reactor Calculations,” Nuclear Engineering and Design, Vol. 236, Issue 3, 295-308, (2006). https://doi.org/10.1016/j.nucengdes.2005.07.004
  19. D'Auria, F., Mazzini, M., Oriolo, F., Paci, S., “Comparison Report of the OECD/CSNI International Standard Problem 21 (Piper-one experiment PO-SB-7),” CSNI Report No. 162, (1989).
  20. A. Prosek, F. D'Auria, B. Mavko, “Review of Quantitative Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM),” Nuclear Engineering and Design, 217, 179-206, (2002). https://doi.org/10.1016/S0029-5493(02)00152-8
  21. B.D. Chung et al., “Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break,” NURETH-10, Seoul, Korea, October 5-9, (2003).
  22. KAERI ATLAS Team, “Meeting minutes of the 4th Progress Review Meeting of the DSP-01,” Muju Ilsung-Condo, (in Korean), 2010.2.25. (2010)
  23. KAERI ATLAS Team, “Meeting minutes of the ATLAS DSP-01 Workshop,” Daejon INTEC, (in Korean), 2010.4.29. (2010)

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