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Journal of Nuclear Science and Technology Volume 58, 2021 - Issue 11
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Article

Estimation of reactor vessel failure by metallic interaction in Fukushima Daiichi Nuclear Power Plant accident

Ayumi Itoha Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology, Tokyo, JapanCorrespondence[email protected]
,
Shintaro Yasuia Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology, Tokyo, Japan;b Laboratory for Materials and Structures, Tokyo Institute of Technology, Yokohama, Japan
&
Yoshinao Kobayashia Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology, Tokyo, Japan
Pages 1235-1243 | Received 12 Feb 2021, Accepted 13 May 2021, Published online: 31 May 2021

References

  • Fujii H, Hara K, Hayashi K, et al. Investigation of the unit-1 nuclear reactor of Fukushima Daiichi by cosmic muon radiography. Prog Theor Exp Phys. 2020;1–14.
  • Yamashita T, Sato I, Honda T, et al. Comprehensive analysis and evaluation of Fukushima Daiichi Nuclear Power station unit 2. Nucl Technol. 2020;206:1517–1537.
  • TEPCO. Locating fuel debris inside the unit 3 reactor using a Muon measurement technology at Fukushima Daiichi Nuclear Power Station [Internet]. 2017 [cited 2021 Feb 6]. Available from: https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2017/images/handouts_170928_01-e.pdf
  • OECD/NEA. Benchmark study of the accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project), Phase I Summary Report, NEA/CSNI/R. 2015.
  • Pellegrini M, Naitoh M, Kudo Y, et al. Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs. Nucl Eng Des. Nucl Eng Des. 2019; 354:110217.
  • Li X, Sato I, Yamaji A, et al. Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident. Ann Nucl Energy. 2021;150:107819.
  • Gauntt RO, Humphries LL Final results of the XR2-1 BWR metallic melt relocation experiment NUREG/CR-6527. 1997.
  • Itoh A, Andrews NC, Luxat DL, et al. Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident. J Nucl Sci Technol. 2021;58(6):676–689.
  • Hofmann P. Current knowledge on core degradation phenomena, a review. J Nucl Mater. 1999;270:194–211.
  • Itoh A, Kobayashi Y, Suzuki A, et al. Thermodynamic approach for determination of fuel relocation condition in severe accident progression. J Nucl Mater. 2020;529:151925.
  • Veshchunov MS, Shestak VE. Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions. Nucl Eng Des. 2008;238:3500–3507.
  • Protopapas P, Andersen HC, Parlee NAD. Theory of transport in liquid metals. I. Calculation of self‐diffusion coefficients. J Chem Phys [Internet]. 1973;59:15–25.
  • TEPCO : Progress reports on the investigation and examination of unconfirmed and unresolved issues [Internet]. [cited 2021 May 3]. Available from: https://www.tepco.co.jp/en/decommision/accident/unsolved-e.html.
  • IAE. Information portal for the Fukushima Daiichi accident analysis and decommissioning activities [Internet]. [cited 2021 Jan 25]. Available from: https://fdada.info/.
  • Pellegrini M, Suzuki H, Mizouchi H, et al. Early phase accident progression analysis of Fukushima Daiichi unit 3 by the SAMPSON code. Nucl Technol. 2014;186:241–254.
  • Fernandez-Moguel L, Rydl A, Lind T. Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis. Ann Nucl Energy. 2019;123:59–77.
  • Kurata M, Ogata T, Nakamura K, et al. Thermodynamic assessment of the Fe-U, U-Zr and Fe-U-Zr systems. J Alloys Compd. 1998;271–273:636–640.
  • Yang Y, Tan L, Bei H, et al. Thermodynamic modeling and experimental study of the Fe-Cr-Zr system. J Nucl Mater. 2013;441:190–202.
  • Palumbo M, Cacciamani G, Bosco E, et al. Thermodynamic analysis of glass formation in Fe-B system. Calphad. 2001;25:625–637.
  • Quaini A, Guéneau C, Gossé S, et al. Contribution to the thermodynamic description of the corium – the U-Zr-O system. J Nucl Mater. 2018;501:104–131.
  • Chen HM, Zheng F, Liu HS, et al. Thermodynamic assessment of B-Zr and Si-Zr binary systems. J Alloys Compd. 2009;468:209–216.
  • Nash BP, Jayanth CS. The Ni-Zr system. Bull Alloy Phase Diagrams. 1982;5:136–140.

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