Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

REFERENCES

• K. C. ROGERS, “Three Mile Island Reactor Pressure Vessel Investigations Project—Achievements and Significant Results,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• R. LONG, Testimony in “The American Experience: Meltdown at Three Mile Island,” Public Broadcasting System Documentary (1999).
   Google Scholar
• E. E. KINTNER, “After Three Mile Island Unit 2—A Decade of Change,” Nucl. Technol, 87, 21 (1989).
   Google Scholar
• W. PASEDAG, “DOE’s TMI-2 Accident Evaluation Program,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• “Three Mile Island Reactor Pressure Vessel Investigation Project, Achievements and Significant Results,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• J. R. WOLF et al., “TMI-2 Vessel Investigation Project Integration Report,” NUREG/CR-6197, U.S. Nuclear Regulatory Commission (1994).
   Google Scholar
• J. S. WALKER, Three Mile Island—A Nuclear Crisis in Historical Perspective,” University of California Press, Berkeley, California, and Los Angeles (2004).
   Google Scholar
• J. HENDRIE, Testimony in “The American Experience: Meltdown at Three Mile Island,” Public Broadcasting System Documentary (1999).
   Google Scholar
• H. DENTON, Testimony in “The American Experience: Meltdown at Three Mile Island,” Public Broadcasting System Documentary (1999).
   Google Scholar
• P. HOFMANN et al., “Reactor Core Materials Interactions at Very High Temperatures,” Nucl. Technol, 87, 146 (1989).
   Google Scholar
• “Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear Safety—The Accident at TEPCO’s Fukushima Nuclear Power Stations,” Government of Japan (June 2011).
   Google Scholar
• “Additional Report of the Japanese Government to the IAEA—The Accident at TEPCO’s Fukushima Nuclear Power Stations (Second Report),” Government of Japan (Sep. 2011).
   Google Scholar
• D. N. CHIEN and D. J. HANSON, “Accident Management Information Needs for a BWR with a MARK I Containment,” NUREG/CR-5702, U.S. Nuclear Regulatory Commission (1991).
   Google Scholar
• “TEPCO Fukushima Update on March 29, 2012 [162]: 2nd Probing Inside the PCV of 1F-2,” Tokyo Electric Power Company Web Site: http://www.tepco.co.jp/en/nu/fukushimanp/images/handouts_120326_07-e.pdf ( current as of Mar. 29, 2012).
   Google Scholar
• “Mid-and-Long-Term Roadmap Towards the Decommissioning of Fukushima Daiichi Nuclear Power Station Units 1–4,” presented at Nuclear Emergency Response Headquarters, Government and TEPCO’s Mid-to-Long Term Countermeasure Mtg., December 21, 2011; Tokyo Electric Power Company Web Site: http://www.tepco.co.jp/en/press/corpcom/release/betu11_e/images/111221e14.pdf ( current as of Apr. 3, 2012).
   Google Scholar
• R. E. HENRY, TMI-2: An Event in Accident Management for Light-Water-Moderated Reactors, American Nuclear Society, La Grange Park, Illinois (2011).
   Google Scholar
• B. B. SCHNITZLER and J. B. BRIGGS, “TMI-2 Isotope Inventory Calculations,” EGG-PBS-6798, EG&G Idaho, Inc., Idaho National Laboratory (1985).
   Google Scholar
• D. W. GOLDEN et al., “Summary of the Three Mile Island Unit 2 Analysis Exercise,” Nucl. Technol, 87, 326 (1989).
   Google Scholar
• M. L. RUSSELL and R. K. McCARDELL, “Three Mile Island Unit 2 Core Geometry, Nucl. Technol, 87, 865 (1989).
   Google Scholar
• R. RAINISCH, “Analysis of Gamma Scanning of In-Core Detector #18 (L-11) in Lower Reactor Vessel Head,” TPO/TMI-175, GPU Nuclear Corporation (June 1985).
   Google Scholar
• M. E. YANCEY, R. D. MEININGER, and L. A. HECKER, “TMI-2 In-Core Instrument Damage—An Update,” GEND-INF-031, Vol. II, EG&G Idaho, Inc., Idaho National Laboratory (1984).
   Google Scholar
• R. GOLD et al., “Solid State Track Recorder Neutron Dosimetry in the Three Mile Island Unit-2 Reactor Cavity,” HEDL-7484, Westinghouse Hanford Company (1985).
   Google Scholar
• V. R. FRICKE, “Core Debris Bed Probing,” TPB 84-8, Rev. 1, GPU Nuclear Corporation (Feb. 1985).
   Google Scholar
• E. L. TOLMAN et al., “TMI-2 Accident Scenario Update,” EGG-TMI-7489, Idaho National Laboratory (1986).
   Google Scholar
• J. M. BROUGHTON et al., “A Scenario of the Three Mile Island Unit 2 Accident,” Nucl. Technol, 87, 34 (1989).
   Google Scholar
• R. L. MOORE, D. W. GOLDEN, and E. L. TOLMAN, “Three Mile Island Unit 2 Degraded Core Heatup and Cooldown Analysis,” Nucl. Technol, 87, 990 (1989).
   Google Scholar
• D. J. N. TAYLOR, “TMI SPND Interpretation,” Proc. 1st Int. Information Mtg. TMI-2 Accident, Germantown, Maryland, October 1985.
   Google Scholar
• C. S. OLSEN, R. R. HOBBINS, and B. A. COOK, “Ap-plication of Severe Fuel Damage Experiments to Evaluating Three Mile Island Unit 2 Core Materials Behavior,” Nucl. Technol, 87, 884 (1989).
   Google Scholar
• A. D. KNIPE, S. A. PLOGER, and D. J. OSETEK, “PBF Severe Fuel Damage Scoping Test—Test Results Report,” NUREG/CR-4683, U.S. Nuclear Regulatory Commission (1986).
   Google Scholar
• J. P. ADAMS and R. P. SMITH, “TMI-2 Lower Plenum Video Data Summary,” EGG-TMI-7429, Idaho National Laboratory (1987).
   Google Scholar
• R. W. GARNER, D. E. OWEN, and M. R. MARTIN, “An Assessment of the TMI-2 Axial Power Shaping Rod Dynamic Test Results,” GEND-INF-038, EG&G Idaho, Inc. (1983).
   Google Scholar
• L. S. BELLER and H. L. BROWN, “Design and Operation of the Core Topography Data Acquisition System for TMI-2,” GEND-INF-012, EG&G Idaho, Inc. (1984).
   Google Scholar
• V. R. FRICKE, “Reactor Lower Head Video Inspection— Phase II,” in “TMI-2 Technical Bulletin TB-86-3, Rev. 0,” GPU Nuclear Corporation (Jan. 8, 1986).
   Google Scholar
• A. M. RUBIN, “Overview and Organization of Three Mile Island Unit 2 Vessel Investigation Project,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• D. W. AKERS and B. K. SCHUETZ, “Physical and Radiochemical Examinations of Debris from the TMI-2 Lower Head,” Nucl. Safety, 35, 2, 288 (1994).
   Google Scholar
• N. COLE, T. FRIEDRICHS, and B. LIPFORD, “Specimens Removed from the Damaged TMI Reactor Vessel,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massa-chusetts, October 20–22, 1993.
   Google Scholar
• D. R. DIERCKS and G. E. KORTH, “Results of Metallographic Examinations and Mechanical Tests of Pressure Vessel Samples from the TMI-2 Lower Head,” Nucl. Safety, 35, 2, 301 (1994).
   Google Scholar
• G. E. KORTH, “Peak Accident Temperatures of the TMI-2 Lower Pressure Vessel Head,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• D. R. DIERCKS and L. A. NEIMARK, “Mechanical Properties and Examination of Cracking in TMI-2 Pressure Vessel Lower Head Material,” Proc. Open Forum Sponsored by the OECD Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission, Boston, Massachusetts, October 20–22, 1993.
   Google Scholar
• L. A. NEIMARK, “Insight into the TMI-2 Core Material Relocation Through Examination of Instrument Tube Nozzles,” Nucl. Safety, 35, 2, 280 (1994).
   Google Scholar
• E. L. TOLMAN, “TMI-2 Accident Evaluation Program,” EGG-TMI-7048, Idaho National Laboratory (1986).
   Google Scholar
• R. R. HOBBINS et al., “Review of Experimental Results on Light Water Reactor Core Melt Progression,” Nucl. Technol, 95, 287 (1991).
   Web of Science ®Google Scholar
• B. R. SEHGAL, “Light Water Reactor (LWR) Safety,” Nucl. Eng. Technol, 38, 697 (2006).
   Google Scholar
• J. L. REMPE et al., “In-Vessel Retention of Molten Co-rium: Lessons Learned and Outstanding Issues,” Nucl. Technol, 161, 210 (2008).
   Web of Science ®Google Scholar
• “MELCOR 1.8.5 User’s Manual andMELCOR 1.8.5 Reference Manual,” NUREG/CR-6119, Vols. 1, 2, and 3; Sandia National Laboratories: http://melcor.sandia.gov ( current as of Apr. (2012).
   Google Scholar
• “MAAP Modular Accident Analysis Program,” Fauske and Associates; http://www.fauske.com/maap.html ( current as of Apr. (2012).
   Google Scholar
• Institute of Applied Energy, Ministry of Economy, Trade, and Industry (METI), IMPACT Project: http://www.iae.or.jp/e/group/safety_analysis.html ( current as of Apr. (2012).
   Google Scholar
• “ICARE/CATHARE: A Computer System Code for Analysis of Severe Accidents in LWRs,” Commissariat à l’énergie atomique et aux énergies alternatives; http://wwwcathare.cea.fr/scripts/home/publigen/content/templates/show.asp?P=130&L=EN&SYNC=Y ( current as of Apr. (2012).
   Google Scholar
• “ATHLET-CD,” Gesellschaft für Anlagen-und Reaktorsicherheit; http://www.grs.de/content/athlet-cd ( current as of Apr. (2012).
   Google Scholar
• M. S. VESHCHUNOV, A. E. KISELEV, and V. F. STRIZHOV, “Development of SVECHA Code for the Modelling of In-Vessel Phase of Severe Accident at Pressurized Water Reactors,” Izvestiya, 2, 6 (2004) ( in Russian).
   Google Scholar
• SCDAP/RELAP5-3D® CODE DEVELOPMENT TEAM, “SCDAP/RELAP5-3D® Code Manuals, Volumes 1–5,” INEEL/EXT-02-00589, Rev. 2.2, Idaho National Laboratory (2003).
   Google Scholar
• K. K. MURATA et al., “Code Manual for CONTAIN 2.0: A Computer Code for Nuclear Reactor Containment Analy-sis,” NUREG/CR-6533, U.S. Nuclear Regulatory Commission (1997).
   Google Scholar
• N. BIXLER, “Victoria 2.0: A Mechanistic Model for Radionuclide Behaviour in a Nuclear Reactor Coolant System Under Severe Accident Conditions,” NUREG/CR-6131, U.S. Nuclear Regulatory Commission (1998).
   Google Scholar
• J. KELLY et al., “Perspectives on Advanced Simulation for Nuclear Reactor Safety Applications,” Nucl. Sci. Eng, 168, 128 (2011).
   Web of Science ®Google Scholar
• J. L. REMPE, “Test Data for US EPR Severe Accident Code Validation,” INL/EXT-06-11326, Rev. 3, Idaho National Laboratory (May 2007).
   Google Scholar
• P. HOFMANN et al., “Chemical-Physical Behavior of Light Water Reactor Core Components Tested Under Severe Reactor Accident Conditions in the CORA Facility,” Nucl. Technol, 118, 200 (1997).
   Web of Science ®Google Scholar
• M. STEINBRUCK et al., “Synopsis and Outcome of the QUENCH Experimental Program,” Nucl. Eng. Des, 240, 1714 (2010).
   Web of Science ®Google Scholar
• R. O. GAUNTT and L. L. HUMPHRIES, “Final Results of the XR2-1 BWR Metallic Melt Relocation Experiment,” NUREG/CR-6527, U.S. Nuclear Regulatory Commission (1997).
   Google Scholar
• R. D. GASSER, R. O. GAUNTT, and S. C. BOURCIER, “Late-Phase Melt Progression Experiment MP-1: Results and Analysis,” NUREG/CR-5874, U.S. Nuclear Regulatory Commission (1996).
   Google Scholar
• R. D. GASSER et al.,“Late-Phase Melt Progression Experiment MP-2: Results and Analysis,” NUREG/CR-6167, U.S. Nuclear Regulatory Commission (1996).
   Google Scholar
• “Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression, and Reflooding—Benchmark Exercise on an Alternative TMI-2 Accident Scenario,” NEA/CSNI/R(2009) 3, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/Committee on the Safety of Nuclear Installations (Aug. 2009).
   Google Scholar
• “OECD MASCA Project: A Project to Investigate Chemical and Fission Product Effects on Thermal Loadings Imposed on the Reactor Vessel by a Convective Corium Pool During a Severe Accident,” Russian Research Center Kurchatov Institute; Web Site: www.nsi.kiae.ru/Mbrief.htm ( current as of Apr. 2012).
   Google Scholar
• “CSNI/RASPLAV Seminar 2000, Summary and Conclusions,” Munich, Germany, November 14-15, 2000, NEA/CSNI/R(2000) 23, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/Committee on the Safety of Nuclear Installations.
   Google Scholar
• D. MAGALLON, I. HUHTINIEMI, and H. HOHMANN, “Lessons Learnt from FARO/TERMOS Corium Melt Quenching Experiments,” Nucl. Eng. Des, 189, 223 (1999).
   Web of Science ®Google Scholar
• D. MAGALLON and I. HUHTINIEMI, “Corium Melt Quenching Tests at Low Pressure and Subcooled Water in FARO,” Nucl. Eng. Des,” 204, 369 (2001).
   Web of Science ®Google Scholar
• D. MAGALLON, “Characteristics of Corium Debris Bed Generated in Large-Scale Fuel-Coolant Interaction Experiments,” Nucl. Eng. Des, 236, 1998 (2006).
   Web of Science ®Google Scholar
• H. HOHMANN et al., “FCI Experiments in the Aluminum Oxide/Water System,” Nucl. Eng. Des, 155, 391 (1995).
   Web of Science ®Google Scholar
• I. HUHTINIEMI and D. MAGALLON, “Insight into Steam Explosions with Corium Melts in KROTOS,” Nucl. Eng. Des, 204, 391 (2001).
   Web of Science ®Google Scholar
• I. HUHTINIEMI, D. MAGALLON, and H. HOHMANN, “Results of Recent KROTOS FCI Tests: Alumina Versus CoriumMelts,” Nucl. Eng. Des, 189, 379 (1999).
   Web of Science ®Google Scholar
• I. HUHTINIEMI, H. HOHMANN, and D. MAGALLON, “FCI Experiments in the Corium/Water System,” Nucl. Eng. Des, 177, 339 (1997).
   Web of Science ®Google Scholar
• T. Y. CHU et al., “Lower Head Failure Experiments and Analyses,” NUREG/CR-5582, U.S. Nuclear Regulatory Commission (1999).
   Google Scholar
• L. L. HUMPHRIES et al., “OECD Lower Head Failure Project Final Report,” OECD/NEA/CSNI/2, p. 27, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/Committee on the Safety of Nuclear Installations (2002).
   Google Scholar
• M. T. FARMER, D. J. KILSDONK, and R. W. AESCHLIMANN, “Corium Coolability Under Ex-Vessel Accident Conditions for LWRs,” Nucl. Eng. Technol, 41, 575 (2009).
   Google Scholar
• D. A. POWERS and F. E. ARELLANO, “Large-Scale, Transient Tests of the Interaction of Molten Steel with Concrete,” NUREG/CR-2282, U.S. Nuclear Regulatory Commission (1982).
   Google Scholar
• D. A. POWERS and F. E. ARELLANO, “Direct Observation of Melt Behavior During High Temperature Melt/Concrete Interactions,” NUREG/CR-2283, U.S. Nuclear Regulatory Commission (1982).
   Google Scholar
• J. K. FINK et al., “Aerosol and Melt Chemistry in the ACE Molten Core-Concrete Interaction Experiments,” High Temperature Mater. Sci, 33, 51 (1995).
   Google Scholar
• D. A. POWERS, J. E. BROCKMANN, and A. W. SHIVER, “VANESA: AMechanistic Model of Radionuclide Release and Aerosol Generation During Core Debris Interactions with Concrete,” NUREG/CR-4308, U.S. Nuclear Regulatory Commission (1986).
   Google Scholar
• S. LOMPERSKI and M. T. FARMER, “Experimental Evaluation of the Water Ingression Mechanism for Corium Cooling,” Nucl. Eng. Des, 237, 905 (2006).
   Google Scholar
• S. LOMPERSKI, M. T. FARMER, and S. BASU, “Experimental Investigation of Corium Quenching at Elevated Pressure,” Nucl. Eng. Des, 236, 2271 (2006).
   Google Scholar
• J. M. BONNET and J. M. SEILER, “Coolability of Corium Spread onto Concrete Under Water, the PERCOLA Model,” Proc. 2nd CSNI Specialists’ Mtg. Core Debris–Concrete Interactions, Karlsruhe, Germany, April 1–3, 1992, Committee on the Safety of Nuclear Installations.
   Google Scholar
• B. TOURNIAIRE and J. M. SEILER, “Modeling of Viscous and Inviscid Fluid Ejection Through Orifices by Sparging Gas,” Proc. 2004 Int. Congress Advances in Nuclear Power Plants (ICAPP ’04), Pittsburgh, Pennsylvania, June 13–17, 2004, American Nuclear Society (2004).
   Google Scholar
• M. T. FARMER, “Phenomenological Modeling of the Melt Eruption Cooling Mechanism During Molten Corium Concrete Interaction (MCCI),” Proc. 2006 Int. Congress Advances in Nuclear Power Plants (ICAPP ’06), Reno, Nevada, June 4–8, 2006, American Nuclear Society (2006).
   Google Scholar
• K. R. ROBB and M. L. CORRADINI, “Melt Eruption Modeling for MCCI Simulations,” Proc. 14th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-14), Toronto, Canada, September 25–30, 2011.
   Google Scholar
• K. R. ROBB and M. L. CORRADINI, “Ex-Vessel Corium Coolability Sensitivity Study with CORQUENCH Code,” Proc. 13th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, September 27–October 2, 2009.
   Google Scholar