Performance evaluation of the SMART passive safety injection system against the SBLOCA scenario with the SMART-ITL facility
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A set of system performance tests has been performed and the thermal-hydraulic behaviors were investigated for the passive safety injection system (PSIS) of the SMART design. Major thermal-hydraulic characteristics of core cooling in reactor coolant system and safety injection (SI) in PSIS were investigated using the SMART-ITL. The parametric effects of break size, break location and train number on the PSIS performance were discussed with the relevant SMART-ITL data. Compared with the 2.0 inch SI line break test, the 0.4 inch SI line break test has a milder change of system parameters. The pressure is reduced more quickly, the decrease of water level is slower and the break mass flow rate is higher during the pressurizer safety valve line break than during the SI line break. Major thermal-hydraulic parameters were compared among single, two and full train operation of the PSIS focusing on the effect of train number. It was shown that multiple trains of CMT and SIT were operated independently and the reactor vessel (RV) inventory increased proportionally with the addition of each train. Sufficient SI water was injected into the RV in a passive manner to cool down the reactor core efficiently during the full train test.
Abstract
A set of system performance tests has been performed and the thermal-hydraulic behaviors were investigated for the passive safety injection system (PSIS) of the SMART design. Major thermal-hydraulic characteristics of core cooling in reactor coolant system and safety injection (SI) in PSIS were investigated using the SMART-ITL. The parametric effects of break size, break location and train number on the PSIS performance were discussed with the relevant SMART-ITL data. Compared with the 2.0 inch SI line break test, the 0.4 inch SI line break test has a milder change of system parameters. The pressure is reduced more quickly, the decrease of water level is slower and the break mass flow rate is higher during the pressurizer safety valve line break than during the SI line break. Major thermal-hydraulic parameters were compared among single, two and full train operation of the PSIS focusing on the effect of train number. It was shown that multiple trains of CMT and SIT were operated independently and the reactor vessel (RV) inventory increased proportionally with the addition of each train. Sufficient SI water was injected into the RV in a passive manner to cool down the reactor core efficiently during the full train test.
참고문헌 (23)
- Major results from validation tests with SMART-ITL on SMART passive safety injection system, "H.S. Park", KAERI, 37~117, pp.KAERI (2022), TR-9609[DOI]
- Experiment on Passive Emergency Core Cooling System Using ATLAS Test Facility, "S. Cho", ~, pp.NURETH-19 (2022)
- R. F. Wright, "Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility", Nucl. Eng. Technol, 39(4), pp.287~298 (2007)
- Jose N. Reyes, "Testing of the multi-application small light water reactor(MASLWR)passive safety systems", Nucl. Eng. Des, 237, pp.1999~2005 (2007)
- K. K. Kim, "SMART : the First licensed advanced integral reactor", J. Energy Power Eng, 8, pp.94~102 (2014)
- H. S. Park, "Contribution of thermal-hydraulic validation tests to the standard design approval of SMART", Nucl. Eng. Technol, 49, pp.1537~1546 (2017)
- Report of Passive Safety System, "Y. M. Bae", KAERI, ~, pp.SER-410-Fs403-SD (2012)
- H.S. Park, "SMR accident simulation in experimental test loop", Nucl. Eng. Int, pp.12~15 (2013)
- H. Bae, "Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactorintegral test loop facility to estimate the safety of the SMART design", Nucl. Eng. Technol, 49, pp.968~978 (2017)
- Y. S. Kim, "Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility", Ann. Nucl. Energy, 113, pp.25~36 (2018)
- H. Bae, "Core makeup tank injection characteristics during different test scenarios using SMART-ITL facility", Ann. Nucl. Energy, 126(10) (2019)
- J.H. Yang, "Comparison of two different sized small-break LOCAs on the passive safety injection line using SMART-ITL data", Nucl. Technol, 206, pp.1421~ (2020)
- H.S. Park, "Thermal-hydraulic research supporting the development of SMART", Nucl. Technol, 209, pp.1617~1635 (2023)
- B. D. Chung, "Development and assessment of multi-dimensional flow models in the thermal-hydraulic system analysis code", MARS KAERI, 2005, pp.3011(2005), 3~25
- B. G. Jeon, "Code validation on a passive safety system test with the SMARTITL facility", J. Nucl. Sci. Technol, 54(3), pp.322~329 (2017)
- B. G. Jeon, "Experimental and analytical investigation on SMART passive safety systems for three 2-inch SBLOCA tests using SMART-ITL", Ann. Nucl. Energy, 188, pp.109835~ (2023)
- M. Ishii, "Scaling laws for thermal-hydraulic system under single phase and two-phase natural circulation", Nucl. Eng. Des, 81, pp.411~425 (1984)
- K. T. Park, "Assessment of MARS for direct contact condensation in the core makeup tank", Journal of Computational Fluids Engineering, 19(1), pp.64~72 (2014)
- S. I. Lee, "Two-Stage Scaling Methodology and Direct Contact Condensation of the Core Makeup Tank in a Passive PWR", Ph.D, pp.2013
- J. Tuunanen, "Analyses of PACTEL passive safety injection experiments GDE21 through GED-25", Nucl. Eng. Des, 180, pp.67~91 (1998)
- Y. J. Chung, "Assessment of TASS", SMR code for a loss of coolant flow transient using results of integral type test facility, 2016, pp.92(1), 1~
- S. J. Ha, "Development of the space code for nuclear power plants", Nucl. Eng. Technol, 43(1), pp.45~62 (2011)
- M. G. Kim, "Development of a special thermal-hydraulic component model for the core makeup tank", Nucl. Eng. Technol, 54, pp.1890~1901 (2022)
