Integral-Effect Test for Loss of Residual Heat Removal System During Mid-Loop Operation in ATLAS Facility

References

• “Loss of Residual Heat Removal (RHR) While at Mid-Loop Conditions Corrective Actions,” NEA/CNRA/R(2006)4, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2006).
   Google Scholar
• D. DUMONT et al., “Loss of Residual Heat Removal During Mid-Loop Operation: BETHSY Experiments,” Nucl. Eng. Des., 149, 1–3, 365 (1994); https://doi.org/10.1016/0029-5493(94)90302-6.
   Web of Science ®Google Scholar
• C. H. LEE et al., “Investigation of Mid-Loop Operation with Loss of RHR at INER Integral System Test (LIST) Facility,” Nucl. Eng. Des., 10 (1996).
   Google Scholar
• S. CARLOS et al., “Analysis of a Loss of Residual Heat Removal System During Mid-Loop Conditions at PKL Facility Using RELAP5/Mod3.3,” Nucl. Eng. Des., 238, 10, 2561 (2008); https://doi.org/10.1016/j.nucengdes.2008.04.013.
   Web of Science ®Google Scholar
• C. QUERAL et al., “Simulation of Loss of RHRs Sequences in PKL Facility with RELAP5 and Trace Codes,” Nucl. Technol., 171, 1, 53 (2010); https://doi.org/10.13182/NT10-A10772.
   Web of Science ®Google Scholar
• H. NAKAMURA, J. KATAYAMA, and Y. KUKITA, “Loss of Residual Heat Removal (RHR) Event During PWR Mid-Loop Operation: ROSA-IV/LSTF Experiment Without Opening on Primary Loop Pressure Boundary,” presented at Winter Annual Meeting of the American Society of Mechanical Engineers, Anaheim, California, November 8–13, 1992, p. 9, American Society of Mechanical Engineers (1992).
   Google Scholar
• Y. UTANOHARA and M. MURASE, “Numerical Analysis of Steam–Air Behavior in a Pressurizer During Reflux Cooling,” Nucl. Eng. Des., 240, 12, 3930 (2010); https://doi.org/10.1016/j.nucengdes.2010.01.005.
   Web of Science ®Google Scholar
• M. M. HOSSEN et al., “Analysis of Loss of RHRS in POSRV Open Case for ATLAS Mid-Loop Test Using MARS-KS Code,” Proc. Spring Mtg. of Korean Nuclear Society, Jeju, Korea, May 17–19, 2017, p. 4, Korean Nuclear Society (2017).
   Google Scholar
• K. CHANG and D. LEE, “An Experimental Investigation of the Air Entrainment in the Shutdown Cooling System During Mid-Loop Operation,” Ann. Nucl. Energy, 22, 9, 611 (1995).
   Web of Science ®Google Scholar
• K. VIEROW, T. WU, and T. NAGAE, “Experimental Investigation of Reflux Condensation Heat Transfer in PWR Steam Generator Tubes in the Presence of Noncondensible Gases,” Proc. 10th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5–9, 2003.
   Google Scholar
• Y. M. MOON, H. C. NO, and Y. S. BANG, “Experimental Study of Liquid Holdup in Pressurizer in Case of Loss-of-Residual-Heat-Removal During Mid-Loop Operation,” Proc. 2001 Korean Nuclear Society Spring Mtg, Cheju, Korea, May 24–25, 2001, p. 119, Korean Nuclear Society.
   Google Scholar
• K. UMMINGER, T. MULL, and B. BRAND, “Integral Effect Tests in the PKL Facility with International Participation,” Nucl. Eng. Technol., 41, 6, 765 (2009); https://doi.org/10.5516/NET.2009.41.6.765.
   Web of Science ®Google Scholar
• Y.-M. FERNG and S.-S. MA, “Investigation of System Responses of the Maanshan Nuclear Power Plant to the Loss of Residual Heat Removal During Midloop Operation Using a RELAP5/MOD3 Simulation,” Nucl. Technol., 116, 2, 160 (1996); https://doi.org/10.13182/NT96-A35297.
   Web of Science ®Google Scholar
• K. W. SEUL, Y. S. BANG, and H. J. KIM, “Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition,” Nucl. Technol., 126, 3, 265 (1999); https://doi.org/10.13182/NT99-A2973.
   Web of Science ®Google Scholar
• C. KIM, Y. LEE, and J. PARK, “SIT Makeup Effect on the Loss of Residual Heat Removal During Mid-Loop Operation,” Trans. Am. Nucl. Soc., 115, 4 (2016).
   Google Scholar
• J. GOU et al., “Analysis of Loss of Residual Heat Removal System for CPR1000 Under Cold Shutdown Operation,” Ann. Nucl. Energy, 105, 25 (2017); https://doi.org/10.1016/j.anucene.2017.03.004.
   Web of Science ®Google Scholar
• H. NAGUMO et al., “Development of PIRT and Verification of RELAP5 Void Model for Application to the Loss-of-RHR Event During Mid-Loop Operation,” Proc. 16th Int. Conf. Nuclear Engineering, Orlando, Florida, May 11–15, 2008, Vol. 3, p. 21, ASME (2008); https://doi.org/10.1115/ICONE16-48064.
   Google Scholar
• T. TORIGE, “Application of BEPU Method to Loss of RHR Event During Mid-Loop Operation: Uncertainty Quantification of RELAP5 Model,” Nucl. Eng. Des., 360, 110475 (2020); https://doi.org/10.1016/j.nucengdes.2019.110475.
   Web of Science ®Google Scholar
• M. SHAKIL et al., “Analysis of Loss of Residual Heat Removal System During Mid-Loop Operation of a 300 MWe PWR,” Prog. Nucl. Energy, 112, 1 (2019); https://doi.org/10.1016/j.pnucene.2018.11.010.
   Web of Science ®Google Scholar
• I. GONZÁLEZ, C. QUERAL, and A. EXPÓSITO, “Phenomenology During the Loss of Residual Heat Removal System at Midloop Conditions with Pressurizer PORVs Open: Associated Boron Dilution,” Ann. Nucl. Energy, 34, 3, 166 (2007); https://doi.org/10.1016/j.anucene.2006.11.014.
   Web of Science ®Google Scholar
• J. BIRCHLEY, T. J. HASTE, and M. RICHNER, “Accident Management Following Loss of Residual Heat Removal During Mid-Loop Operation in a Westinghouse Two-Loop PWR,” Nucl. Eng. Des., 238, 9, 2173 (2008); https://doi.org/10.1016/j.nucengdes.2008.02.009.
   Web of Science ®Google Scholar
• J. B. LEE, “Description Report of ATLAS Facility and Instrumentation (Third Revision),” KAERI/TR-8106/2020, Korea Atomic Energy Research Institute (2020).
   Google Scholar
• K. Y. CHOI, “Scaling Analysis Report of the ATLAS Facility,” KAERI/TR-5645/2014, Korea Atomic Energy Research Institute (2014).
   Google Scholar
• Y. S. KIM, W. P. BAEK, and C. H. SONG, “Startup Test Report of ATLAS,” KAERI/TR-3330/2007, Korea Atomic Energy Research Institute (2007).
   Google Scholar
• H. S. PARK et al., “Calculation Sheet for the Basic Design of the ATLAS Fluid System,” KAERI/TR-3333/2007, Korea Atomic Energy Research Institute (2007).
   Google Scholar
• S. CHO, “Description of the Data Acquisition-Control System and Instrumentation of the ATLAS Test Facility,” Proc. 3rd Sino-Korea Workshop in Nuclear Reactor Thermal Hydraulics (WORTH-3), Chengdu, China, August 22–24, 2007.
   Google Scholar
• I.-C. CHU et al., “Development of Passive Flow Controlling Safety Injection Tank for APR1400,” Nucl. Eng. Des., 238, 1, 200 (2008); https://doi.org/10.1016/j.nucengdes.2007.07.002.
   Web of Science ®Google Scholar