Evaluation of Molten Corium Spreading and Sedimentation Behaviors Within Primary Containment Vessel in Unit 3 of Fukushima Daiichi Nuclear Power Plant Toward the Best Prediction of Fuel Debris Distribution

References

• “Fukushima Daiichi Nuclear Power Station Unit 1 Primary Containment Vessel Internal Investigation Completion of the Detailed Visual Investigation of the Perimeter of the Pedestal Using Submersible ROV-A2,” Tokyo Electric Power Company Holdings Inc. (2022); https://www.tepco.co.jp/en/hd/decommission/information/newsrelease/reference/pdf/2022/reference_20220523_01-e.pdf (accessed Apr. 19, 2023).
   Google Scholar
• “Unit 3 Primary Containment Vessel Internal Investigation,” Tokyo Electric Power Company Holdings Inc. (2017); https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2017/images/handouts_171130_03-e.pdf (accessed Apr. 19, 2023).
   Google Scholar
• “Fukushima Daiichi Nuclear Power Station Unit 2 Primary Containment Vessel Internal Investigation Results,” Tokyo Electric Power Company Holdings Inc.; https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2018/images/handouts_180201_01-e.pdf (accessed Apr. 19, 2023).
   Google Scholar
• E. PORCHERON et al., “Fukushima Daiichi Fuel Debris Retrieval: Results of Aerosol Characterization During Laser Cutting of Non-Radioactive Corium Simulants,” J. Nucl. Sci. Technol., 58, 1, 87 (2021); https://doi.org/10.1080/00223131.2020.1806135.
   Web of Science ®Google Scholar
• Q. ZHOU et al., “Microparticles with Diverse Sizes and Morphologies from Mechanical and Laser Cutting of Fuel Debris Simulants and Geopolymer as a Covering Material,” J. Nucl. Sci. Technol., 58, 4, 461 (2021); https://doi.org/10.1080/00223131.2020.1869623.
   Web of Science ®Google Scholar
• H. LIANG et al., “Effect of Spray Properties on Aerosol Scavenging Efficiency with Water Mist,” J. Aero. Sci., 159, 105853 (2022); https://doi.org/10.1080/02786826.2021.1966377.
   Web of Science ®Google Scholar
• H. LIANG et al., “Numerical Simulation of Aerosol Generation by Cutting Fuel Debris and Aerosol Removal by Spray Droplets During Fukushima Decommissioning,” Prog. Nucl. Energy., 160, 104667 (2023); https://doi.org/10.1016/j.pnucene.2023.104667.
   Web of Science ®Google Scholar
• N. SATO, A. KIRISHIMA, and D. AKIYAMA, “Study on Fuel Debris and Its Waste Management for Fukushima Dai-ichi Nuclear Power Plant Accident—Research on RI/Nuclear Materials and Management of Facility,” Radioisotopes, 67, 12, 591 (2018); https://doi.org/10.3769/radioisotopes.67.591.
   Google Scholar
• “3D Reconstruction Results Based on Unit 3 Primary Containment Vessel Internal Investigation,” Tokyo Electric Power Company Holdings Inc. (2018); https://photo.tepco.co.jp/en/date/2018-e/201804-e/180426-02e.html (accessed Apr. 19, 2023).
   Google Scholar
• “After the Accident at the Fukushima Daiichi Nuclear Power Plant Estimation of the State in the Pressure Vessel and Containment Vessel of the Reactor,” Tokyo Electric Power Company Holdings Inc. (2021); https://www.tepco.co.jp/decommission/information/accident_unconfirmed/pdf/20210719.pdf (accessed Apr. 19, 2023).
   Google Scholar
• M. PELLEGRINI et al., “Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project,” Nucl. Technol., 206, 9, 1449 (2020); https://doi.org/10.1080/00295450.2020.1724731.
   Web of Science ®Google Scholar
• M. PELLEGRINI et al., “Benchmark Study of the Accident at the Fukushima Daiichi NPS: Best-Estimate Case Comparison,” Nucl. Technol., 196, 2, 198 (2016); https://doi.org/10.13182/NT16-63.
   Web of Science ®Google Scholar
• “Summary Report: Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant,” Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2021); https://www.oecd-nea.org/upload/docs/application/pdf/2021-09/7525_bsaf.pdf (accessed Apr. 19, 2023).
   Google Scholar
• R. E. HENRY, C. Y. PAIK, and M. G. PLYS, “MAAP4-Modular Accident Analysis Program for LWR Power Plants,” Research Project 3131-02, Electric Power Research Institute (1994).
   Google Scholar
• L. HUMPHRIES et al., MELCOR Computer Code Manuals, Sandia National Laboratories, Albuquerque, New Mexico (2015).
   Google Scholar
• H. UJITA et al., “Development of Severe Accident Analysis Code SAMPSON in IMPACT Project,” J. Nucl. Sci. Technol., 36, 11, 1076 (1999); https://doi.org/10.1080/18811248.1999.9726300.
   Web of Science ®Google Scholar
• K. ABE et al., “Development of Computer Code System THALES for Thermal-Hydraulic Analysis of Core Meltdown Accident, (I),” J. At. Energy Soc. Japan, 27, 11, 1035 (1985); https://doi.org/10.3327/jaesj.27.1035.
   Web of Science ®Google Scholar
• S. KOSHIZUKA and Y. OKA, “Moving-Particle Semi-Implicit Method for Fragmentation of Incompressible Fluid,” Nucl. Sci. Eng, 123, 3, 421 (1996); https://doi.org/10.13182/NSE96-A24205.
   Web of Science ®Google Scholar
• N. TAKAHASHI et al., “Development of MPS Method and Analytical Approach for Investigating RPV Debris Bed and Lower Head Interaction in 1F Units-2 and 3,” Nucl. Eng. Des., 379, 111244 (2021); https://doi.org/10.1016/j.nucengdes.2021.111244.
   Web of Science ®Google Scholar
• T. FUKUDA et al., “Analysis of the Localized Metallic Phase Solidification in VULCANO VF-U1 with MPS Method,” Nucl. Eng. Des., 385, 111537 (2021); https://doi.org/10.1016/j.nucengdes.2021.111537.
   Web of Science ®Google Scholar
• X. LI et al., “Estimation of Fukushima Daiichi Nuclear Power Plant Unit-3 with Moving Particle Semi-Implicit Method (MPS) Method,” Ann. Nucl. Energy, 169, 108923 (2022); https://doi.org/10.1016/j.anucene.2021.108923.
   Web of Science ®Google Scholar
• M. KONDO, “A Physically Consistent Particle Method for Incompressible Fluid Flow Calculation,” Comput. Part. Mech., 8, 69 (2021); https://doi.org/10.1007/s40571-020-00313-w.
   Web of Science ®Google Scholar
• M. KONDO et al., “A Physically Consistent Particle Method for High-Viscous Free-Surface Flow Calculation,” Comput. Part. Mech., 9, 265 (2022); https://doi.org/10.1007/s40571-021-00408-y.
   Web of Science ®Google Scholar
• M. KONDO and J. MATSUMOTO, “Surface Tension and Wettability Calculation Using Density Gradient Potential in a Physically Consistent Particle Method,” Comput. Methods Appl. Mech. Eng., 385, 114072 (2021); https://doi.org/10.1016/j.cma.2021.114072.
   Web of Science ®Google Scholar
• R. YOKOYAMA et al., “Analysis of Molten Metal Spreading and Solidification Behaviors Utilizing Moving Particle Full-Implicit Method,” Front. Energy, 15, 959 (2021); https://doi.org/10.1007/s11708-021-0753-0.
   Web of Science ®Google Scholar
• R. YOKOYAMA et al., “Investigation of the Outflow and Spreading-Solidification Behaviour of Stratified Molten Metal,” J. Nucl. Eng., 2, 168 (2021); https://doi.org/10.3390/jne2020017.
   Google Scholar
• R. YOKOYAMA et al., “A Lagrangian Approach to Ex-Vessel Corium Spreading over Ceramics and Concrete Substrates Using a Moving Particle Hydrodynamics,” Nucl. Eng. Des., 399, 112029 (2022); https://doi.org/10.1016/j.nucengdes.2022.112029.
   Web of Science ®Google Scholar
• R. YOKOYAMA et al., “Simulating Melt Spreading into Shallow Water Using Moving Particle Hydrodynamics with Turbulence Model,” Comput. Part. Mech., 10, 677 (2023); https://doi.org/10.1007/s40571-022-00520-7.
   Web of Science ®Google Scholar
• M. RAMACCIOTTI et al., “Viscosity Models for Corium Melts,” Nucl. Eng. Des., 204, 1–3, 377 (2001); https://doi.org/10.1016/S0029-5493(00)00328-9.
   Web of Science ®Google Scholar
• J. SMAGORINSKY, “General Circulation Experiments with the Primitive Equations: I. The Basic Experiment,” Mon. Weather Rev., 91, 99 (1963); https://doi.org/10.1175/1520-0493(1963)091<0099:gcewtp>2.3.CO;2.
   Google Scholar
• “Information Portal for the Fukushima Daiichi Accident Analysis and Decommissioning Activities (Fdada.info)”; https://fdada.info/en/home2/graph2/graph_tool-en/ (accessed Apr. 20, 2023).
   Google Scholar
• K. OKUMURA et al., “Nuclear Data for Severe Accident Analysis and Decommissioning of Nuclear Power Plant,” Proc. 2012 Symp. Nuclear Data, Kumatori, Osaka, Japan, November 15–16, 2012, p. 15 ( 2012); https://doi.org/10.11484/jaea-conf-2013-002.
   Google Scholar
• I. SATO et al., “Estimation of Long-Term Ex-Vessel Debris Cooling Behavior in Fukushima Daiichi Nuclear Power Plant Unit 3,” Mech. Eng. J., 9, 2, 21 (2022); https://doi.org/10.1299/mej.21-00436b.
   Web of Science ®Google Scholar
• I. SATO, “Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 Pressure Data and Obtained Insights on Accident Progression Behavior,” Nucl. Eng. Des., 383, 111426 (2021); https://doi.org/10.1016/j.nucengdes.2021.111426.
   Web of Science ®Google Scholar
• X. Y. HU and N. A. ADAM, “Angular-Momentum Conservative Smoothed Particle Dynamics for Incompressible Viscous Flows,” Phys. Fluids, 18, 101702 (2006); https://doi.org/10.1063/1.2359741.
   Web of Science ®Google Scholar
• “Convective Heat Transfer,” Engineering ToolBox; https://www.engineeringtoolbox.com/convective-heat-transfer-d_430.html (accessed Apr. 20, 2023).
   Google Scholar
• M. JAMIALAHMADI, C. BRANCH, and C. MULLER-STEINHAGEN, “Augmentation of Nucleate Boiling by Additives,” Trans. Pheno. Heat Mass Trans., 539, (1992); https://doi.org/10.1016/B978-0-444-89851-7.50052-2.
   Google Scholar
• C. JOURNEAU et al., “Ex-Vessel Corium Spreading: Results from the VULCANO Spreading Tests,” Nucl. Eng. Des., 223, 75 (2003); https://doi.org/10.1016/S0029-5493(02)00397-7.
   Web of Science ®Google Scholar
• M. KURATA et al., “Step-by-Step Challenge of Debris Characterization for the Decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS),” J. Nucl. Sci. Technol., 59, 7, 807 (2022); https://doi.org/10.1080/00223131.2022.2040393.
   Web of Science ®Google Scholar
• M. JOHNSON et al., “High-Temperature Ex-Vessel Corium Spreading. Part 1: Experimental Investigations on Ceramic and Sacrificial Concrete Substrates,” J. Nucl. Sci. Technol., 59, 4, 459 (2021); https://doi.org/10.1080/00223131.2021.1977199.
   Web of Science ®Google Scholar
• Y. XIANG et al., “An Experimental Investigation on Debris Bed Formation from Fuel Coolant Interactions of Metallic and Oxidic Melts,” Appl. Therm. Eng., 233, 121186 (2023); https://doi.org/10.1016/j.applthermaleng.2023.121186.
   Web of Science ®Google Scholar
• H. KOKUBO et al., “Viscosity Measurement of Nickel and Stainless Steel Aiming at Systematic Viscosity Measurement for Molten Mixture of Stainless Steel and Boron-Carbide,” J. Japan. Inst. Metals., 82, 400 (2018); https://doi.org/10.2320/jinstmet.JAW201812.
   Web of Science ®Google Scholar