Development of the Penetration Tube Failure Analysis Program in the Lower Head of the Reactor Vessel During a Severe Accident

References

• H. NA et al., “One-Dimensional Ex-Vessel Coolability Analysis of Debris Beds Formed in OPR1000 Pre-Flooded Reactor Cavity,” Ann. Nucl. Energy, 138, 107123 (2020); https://doi.org/https://doi.org/10.1016/j.anucene.2019.107123.
   Web of Science ®Google Scholar
• J. P. HOSEMANN, H. HIRSCHMANN, and H. KOTTOWSKI, “Corium Vessel Interaction Studies—Status of the CORVIS Project,” Proc. 21st Water Reactor Safety Information Mtg., Bethesda, Maryland, October 25–27, 1993, p. 377; NUREG/ CP-0132, Vol. 2, p. 10-3, U.S. Nuclear Regulatory Commission (1994).
   Google Scholar
• S. M. AN and H. Y. KIM, “Revisit of Penetration Failure Models and Calculations for APR1400 ICI Penetrations,” Proc. Korean Nuclear Society Autumn Mtg., Gyeongju, Korea, October 24–25, 2013, Korean Nuclear Society (2013).
   Google Scholar
• B. R. SEHGAL, A. THEERTHAN, and A. GIRI, “Assessment of Reactor Vessel Integrity (ARVI),” Nucl. Eng. Des., 221, 1–3, 23 (2003); https://doi.org/https://doi.org/10.1016/S0029-5493(02)00343-6.
   Web of Science ®Google Scholar
• K. VINCENT, C. CATALDO, and N. LAETITIA, “Study of Tearing Behaviour of a PWR Reactor Pressure Vessel Lower Head Under Severe Accident Loadings,” Nucl. Eng. Des., 238, 9, 2411 (2008); https://doi.org/https://doi.org/10.1016/j.nucengdes.2008.03.005.
   Web of Science ®Google Scholar
• X. GAUS-LIU et al., “In-Vessel Melt Pool Coolability Test—Description and Results of LIVE Experiments,” Nucl. Eng. Des., 240, 11, 3898 (2010); https://doi.org/https://doi.org/10.1016/j.nucengdes.2010.09.001.
   Web of Science ®Google Scholar
• K. VINCENT, F. FLORIAN, and W. HANS-GEORG, “Progress on PWR Lower Head Failure Predictive Models,” Nucl. Eng. Des., 238, 9, 2420 (2008); https://doi.org/https://doi.org/10.1016/j.nucengdes.2008.03.004.
   Web of Science ®Google Scholar
• V. KOUNDY et al., “Simplified Modeling of a PWR Reactor Pressure Vessel Lower Head Failure in the Case of a Severe Accident,” Nucl. Eng. Des., 235, 8, 835 (2005); https://doi.org/https://doi.org/10.1016/j.nucengdes.2004.11.012.
   Web of Science ®Google Scholar
• J. L. REMPE et al., “Light Water Reactor Lower Head Failure Analysis,” NUREG/CR-5642, U.S. Nuclear Regulatory Commission (1993).
   Google Scholar
• R. O. GAUNTT et al., “MELCOR Computer Code Manuals Vol.2: Reference Manuals Version1.8.5,” COR-RM 103-106, Sandia National Laboratories, NUREG/CR-6119, U.S. Nuclear Regulatory Commission (2000).
   Google Scholar
• “MAAP5 (Modular Accident Analysis Program), User’s Manual, Rev.0,” Fauske & Associates (Nov. 2008).
   Google Scholar
• J.-H. PARK, H. Y. KIM, and K. S. HA, “Analysis Program for Evaluating the Failure Mode of Penetration Tube: PENTAP,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 29–30, 2014.
   Google Scholar
• J. JUNG, S. M. AN, and H. Y. KIM, “Numerical Simulation of the Penetration Tube Ejection Using PENTAP Plus,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 2016.
   Google Scholar
• S. M. AN, J. JUNG, and H. Y. KIM, “Experimental Investigations on Penetration Failure by Tube Ejection for an APR1400 ICI Nozzle During a Severe Accident,” Ann. Nucl. Energy, 149, 107810 (2020); https://doi.org/https://doi.org/10.1016/j.anucene.2020.107810.
   Web of Science ®Google Scholar
• R. PARK et al., “Corium Behavior in the Lower Plenum of the Reactor Vessel Under IVR-ERVC Condition: Technical Issues,” Nucl. Eng. Technol., 44, 3, 237 (Apr. 2012); https://doi.org/https://doi.org/10.5516/NET.03.2012.701.
   Web of Science ®Google Scholar
• S. M. AN et al., “Experimental Investigation on APR1400 In-Core Instrumentation Penetration Failure During a Severe Accident,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP-2015), Nice, France, May 3–6, 2015.
   Google Scholar
• S. M. AN, J. JUNG, and H. Y. KIM, “APR1400 In-Core Instrumentation Penetration Failure by Zirconia Melt,” Trans. Am. Nucl. Soc., 114, 868 (2016).
   Google Scholar
• S. M. AN, J. B. LEE, and H. Y. KIM, “Tube Ejection Experiment for an APR1400 ICI Penetration Tube Under ERVC Condition,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18–19, 2017.
   Google Scholar
• S. M. AN et al., “An Experimental Investigation on the Interaction of Molten Corium with Structures,” Proc. 8th Int. Conf. Multiphase Flow (ICMF 2013), Jeju, Korea, May 26–31, 2013.
   Google Scholar
• S. M. AN et al., “Interaction Experiments of Molten Corium with Structures in a Severe Accident,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP 2014), Charlotte, North Carolina, April 6–9, 2014, American Nuclear Society (2014).
   Google Scholar
• F. P. INCROPERA and D. P. DEWITT, Fundamentals of Heat and Mass Tranfser, 5th ed., Wiley (2002).
   Google Scholar
• R. W. OSTENSEN et al., “Fuel Flow and Freezing in the Upper Subassembly Structure Following an LMFBR Disassembly,” Trans. Am. Nucl. Soc., 18, 214 (1974).
   Google Scholar
• M. EPSTEIN et al., “Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel,” Nucl. Sci. Eng., 61, 3, 310 (1976); https://doi.org/https://doi.org/10.13182/NSE76-A26917.
   Web of Science ®Google Scholar
• R. J. HAMMERSLEY and R. E. HENRY, “Experiments to Address Lower Plenum Response Under Severe Accident Conditions,” EPRI-TR-103389-V2P1, Vol. 1, p. 165, Electric Power Research Institute (1994).
   Google Scholar
• F. C. GILES and E. P. DONALD, Materials Science and Engineering, ASM International (1991).
   Google Scholar
• “INCONEL® Alloy 690,” Publication Number SMC-079, Special Metals Corporation; https://www.specialmetals.com/documents/technical-bulletins/inconel/inconel-alloy-690.pdf ( Oct. 2009) (current as of Jan. 29, 2021).
   Google Scholar
• “Evaluation of Tube Ejection Failure for APR1400 ICI Penetration at Various Experimental Conditions,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12–13, 2016.
   Google Scholar
• J. JUNG et al., “Evaluation on Heat Flux Distribution at the Inner and Outer Reactor Vessel Walls Under IVR-ERVC Condition,” Nucl. Eng. Technol., 47, 1, 66 (Feb. 2015); https://doi.org/https://doi.org/10.1016/j.net.2014.11.005.
   Web of Science ®Google Scholar
• D. SON et al., “Development of Computational Module for Transient Behavior of Corium Pool in the Lower Plenum as a Part of Severe Accident Analysis Code in Korea,” Proc. Int. Workshop Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration (SAMRC 2015), Daejeon, Korea, November 9–11, 2015.
   Google Scholar