A VTT Fukushima Daiichi Unit 3 (1F3) method for estimation of liquids and consequences of releases (MELCOR) model was modified to simulate the Fukushima Daiichi Unit 2 (1F2) accident. Five simulations were performed using different modeling approaches. The model 1F2 v1 includes only the basic modifications to reproduce the 1F2 accident. The model 1F2 v2 includes the same modifications used in 1F2 v1 plus the wet well (WW) improvement. In the 1F2 v3 model, the reactor core isolation cooling (RCIC) system logic was modified to avoid the use of tabular functions for the mass flow inlet and outlet. Because of this analysis, it is concluded that there is a strong dependency on parameters that still have many uncertainties, such as the RCIC two-phase flow operation, the alternative water injection, the suppression pool (SP) behavior, the rupture disk behavior and the containment failure modes, which affect the final state of the reactor core.
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April 2018
Research-Article
Fukushima Unit 2 Accident Simulation With MELCOR 2.1
Rafael Bocanegra,
Rafael Bocanegra
Departamento de Ingeniería Energética,
Universidad Politécnica de Madrid,
C/José Gutiérrez Abascal, 2,
Madrid 28006, Spain
e-mail: r.bocanegra@upm.es
Universidad Politécnica de Madrid,
C/José Gutiérrez Abascal, 2,
Madrid 28006, Spain
e-mail: r.bocanegra@upm.es
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Valentino Di Marcello,
Valentino Di Marcello
Instituts für Neutronenphysik und
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: valentino.marcello@kit.edu
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: valentino.marcello@kit.edu
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Victor H. Sánchez-Espinoza,
Victor H. Sánchez-Espinoza
Instituts für Neutronenphysik und
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: victor.sanchez@kit.edu
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: victor.sanchez@kit.edu
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Gonzalo Jiménez
Gonzalo Jiménez
Departamento de Ingeniería Energética,
Universidad Politécnica de Madrid,
Madrid 28006, Spain
e-mail: gonzalo.jimenez@upm.es
Universidad Politécnica de Madrid,
Madrid 28006, Spain
e-mail: gonzalo.jimenez@upm.es
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Rafael Bocanegra
Departamento de Ingeniería Energética,
Universidad Politécnica de Madrid,
C/José Gutiérrez Abascal, 2,
Madrid 28006, Spain
e-mail: r.bocanegra@upm.es
Universidad Politécnica de Madrid,
C/José Gutiérrez Abascal, 2,
Madrid 28006, Spain
e-mail: r.bocanegra@upm.es
Valentino Di Marcello
Instituts für Neutronenphysik und
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: valentino.marcello@kit.edu
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: valentino.marcello@kit.edu
Victor H. Sánchez-Espinoza
Instituts für Neutronenphysik und
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: victor.sanchez@kit.edu
Reaktortechnik (INR),
Karlsruher Institut für Technology,
Karlsruhe 76344, Germany
e-mail: victor.sanchez@kit.edu
Gonzalo Jiménez
Departamento de Ingeniería Energética,
Universidad Politécnica de Madrid,
Madrid 28006, Spain
e-mail: gonzalo.jimenez@upm.es
Universidad Politécnica de Madrid,
Madrid 28006, Spain
e-mail: gonzalo.jimenez@upm.es
Manuscript received September 26, 2017; final manuscript received September 12, 2017; published online March 5, 2018. Assoc. Editor: Asif Arastu.
ASME J of Nuclear Rad Sci. Apr 2018, 4(2): 020908 (9 pages)
Published Online: March 5, 2018
Article history
Received:
September 26, 2016
Revised:
September 12, 2017
Citation
Bocanegra, R., Di Marcello, V., Sánchez-Espinoza, V. H., and Jiménez, G. (March 5, 2018). "Fukushima Unit 2 Accident Simulation With MELCOR 2.1." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 020908. https://doi.org/10.1115/1.4038062
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