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Nuclear Technology Volume 186, 2014 - Issue 2
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Technical Paper

Analysis of Accident Progression with the SAMPSON Code in Fukushima Daiichi Nuclear Power Plant Unit 2

Hiroaki SuzukiInstitute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan
,
Masanori NaitohInstitute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan
,
Atsuo TakahashiInstitute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan
,
Marco PellegriniInstitute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan
&
Hidetoshi OkadaInstitute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan
Pages 255-262 | Published online: 20 Mar 2017

REFERENCES

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  • H. UJITA et al., “Development of Debris Coolability Analysis Module in Severe Accident Analysis Code SAMPSON for IMPACT Project,” J. Nucl. Sci. Technol, 36, 10, 940 (1999); http://dx.doi.org/10.1080/18811248.1999.9726284.
  • H. UJITA and M. HIDAKA, “Model Verification of the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON,’” J. Nucl. Sci. Technol, 38, 4, 229 (2001); http://dx.doi.org/10.1080/18811248.2001.9715025.
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  • M. HIDAKA et al., “Verification of Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON,’ (II),” J. Nucl. Sci. Technol, 39, 5, 520 (2002); http://dx.doi.org/10.1080/18811248.2002.9715230.
  • T. IKEDA et al., “Analysis of International Standard Problem No. 45, QUENCH06 Test at FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON,” J. Nucl. Sci. Technol, 40, 4, 246 (2003); http://dx.doi.org/10.1080/18811248.2003.9715355.
  • T. IKEDA et al., “Analysis of Core Degradation and Fission Products Release in Phebus FPT1 Test at IRSN by Detailed Severe Accidents Analysis Code, IMPACT/ SAMPSON,” J. Nucl. Sci. Technol, 40, 8, 591 (2003); http://dx.doi.org/10.1080/18811248.2003.9715396.
  • N. SATOH et al., “Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON,” J. Nucl. Sci. Technol, 37, 3, 225 (2000); http://dx.doi.org/10.1080/18811248.2000.9714888.
  • “Estimation of Core and Primary Containment Vessel Conditions by MAAP Code,” Tokyo Electric Power Company (2012) (in Japanese).
  • “Fukushima Dai-ichi Nuclear Power Plant—Impact on the Reactor Facility After the Tohoku-Pacific Ocean Earthquake,” Tokyo Electric Power Company (2011) (in Japanese).
  • “Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear Safety—The Accident at TEPCO’s Fukushima Nuclear Power Station,” Nuclear Emergency Response Headquarters (2011).
  • T. Y. CHU et al., “Lower Head Failure Experiment and Analyses,” NUREG/CR-5582, SAND98-2047, Sandia National Laboratories (1999).
  • 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 (2012); http://dx.doi.org/10.5516/NET.03.2012.701.

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