본문 바로가기
KERD
논문KCI 등재

Performance evaluation of the SMART passive safety injection system against the SBLOCA scenario with the SMART-ITL facility

1

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

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)

  1. 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]
  2. Experiment on Passive Emergency Core Cooling System Using ATLAS Test Facility, "S. Cho", ~, pp.NURETH-19 (2022)
  3. 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)
  4. Jose N. Reyes, "Testing of the multi-application small light water reactor(MASLWR)passive safety systems", Nucl. Eng. Des, 237, pp.1999~2005 (2007)
  5. K. K. Kim, "SMART : the First licensed advanced integral reactor", J. Energy Power Eng, 8, pp.94~102 (2014)
  6. H. S. Park, "Contribution of thermal-hydraulic validation tests to the standard design approval of SMART", Nucl. Eng. Technol, 49, pp.1537~1546 (2017)
  7. Report of Passive Safety System, "Y. M. Bae", KAERI, ~, pp.SER-410-Fs403-SD (2012)
  8. H.S. Park, "SMR accident simulation in experimental test loop", Nucl. Eng. Int, pp.12~15 (2013)
  9. 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)
  10. Y. S. Kim, "Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility", Ann. Nucl. Energy, 113, pp.25~36 (2018)
  11. H. Bae, "Core makeup tank injection characteristics during different test scenarios using SMART-ITL facility", Ann. Nucl. Energy, 126(10) (2019)
  12. 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)
  13. H.S. Park, "Thermal-hydraulic research supporting the development of SMART", Nucl. Technol, 209, pp.1617~1635 (2023)
  14. 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
  15. 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)
  16. 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)
  17. M. Ishii, "Scaling laws for thermal-hydraulic system under single phase and two-phase natural circulation", Nucl. Eng. Des, 81, pp.411~425 (1984)
  18. 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)
  19. S. I. Lee, "Two-Stage Scaling Methodology and Direct Contact Condensation of the Core Makeup Tank in a Passive PWR", Ph.D, pp.2013
  20. J. Tuunanen, "Analyses of PACTEL passive safety injection experiments GDE21 through GED-25", Nucl. Eng. Des, 180, pp.67~91 (1998)
  21. 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~
  22. S. J. Ha, "Development of the space code for nuclear power plants", Nucl. Eng. Technol, 43(1), pp.45~62 (2011)
  23. M. G. Kim, "Development of a special thermal-hydraulic component model for the core makeup tank", Nucl. Eng. Technol, 54, pp.1890~1901 (2022)

관련 논문AI추천

Integral effect tests for intermediate and small break loss-of-coolant accidents with passive emergency core cooling system조석, 강경호, 김종록, 박유선, 배병언, 이재봉한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제7호Overview of separate effect and integral system tests on the passive containment cooling system of SMART100배황, 강경호, 권진수, 박현식, 손홍현, 안태환, 양진화한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제3호Experimental investigation and validation of TASS/SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility배황, 박현식, 윤은구, 임성원, 전지한, 정영종한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제2호Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART김상호, 김성일, 김환열, 박래준, 이병희, 정재훈, 함재현한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제12호Investigation of condensation with non-condensable gas in natural circulation loop for passive safety system배황, 박현식, 안태환, 양진화한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제3호Severe accident analysis induced by secondary pipeline break in a small modular PWRBi Xiaolong, Chen Jie, Sun Peiwei, Wei Xinyu한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제10호

이 간행물의 다른 논문 (49건)