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Article

Leaching behavior of multiphase solidified melt prepared from stainless steel and Zircaloy

Pages 768-780 | Received 12 May 2021, Accepted 17 Nov 2021, Published online: 09 Jan 2022

References

  • Koma Y, Shibata A, Ashida T. Radioactive contamination of several materials following the Fukushima Daiichi Nuclear Power Station accident. Nucl Mater Energy. 2017;10:35–41.
  • Shibata A, Koma Y, Ohi T. Estimation of the inventory of the radioactive wastes in Fukushima Daiichi NPS with a radionuclide transport model in the contaminated water. J Nucl Sci Technol. 2016;53:1933–1942.
  • Nuclear Damage Compensation and Decommissioning Facilitation Corporation. Technical strategic plan 2020 for decommissioning of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings, Inc. Japan: Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF); 2020 Accessed 30 Mar 2021. https://www.dd.ndf.go.jp/files/user/pdf/en/strategic-plan/book/20201214_SP2020eFT.pdf.
  • Task Force on Research Strategy for Debris of Fukushima Daiichi Nuclear Power Station. Analysis of debris samples of Tokyo Electric Power Company Holdings Fukushima Daiichi Nuclear Power Station (Translated document). Japan: Japan Atomic Energy Agency; 2020. JAEA-Review 2020-055.
  • Inagaki K, Sonoda T, Ogata T, et al. Examination of stability of molten and damaged materials from TMI-2 and irradiated fuel sample. Komae (Japan): Central Research Institute of Electric Power Industry; 2016. L15006. [in Japanese].
  • Zubekhina BY, Burakov BE. Leaching of actinides and other radionuclides from matrices of Chernobyl “lava” as analogues of vitrified HLW. J Chem Thermodyn. 2017;114:25–29.
  • Onishi T, Maeda K, Katsuyama K. Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS. J Nucl Sci Technol. 2020. DOI:https://doi.org/10.1080/00223131.2020.1822943
  • Nakayoshi A, Fegou C, De Windt L, et al. Leaching behavior of prototypical corium samples: a step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors. Nucl Eng Des. 2020;360:110522.
  • Sasaki T, Sakamoto S, Akiyama D, et al. Leaching behavior of gamma-emitting fission products, calcium, and uranium from simulated MCCI debris in water. J Nucl Sci Technol. 2019;56:1092–1102.
  • Sasaki T, Takeno Y, Kobayashi T, et al. Leaching behavior of gamma-emitting fission products and Np from neutron-irradiated UO2–ZrO2 solid solutions in non-filtered surface seawater. J Nucl Sci Technol. 2016;53:303–311.
  • Sasaki T, Takeno Y, Kirishima T, et al. Leaching test of gamma-emitting Cs, Ru, Zr, and U from neutron-irradiated UO2/ZrO2 solid solutions in non-filtered surface seawater. J Nucl Sci Technol. 2015;52:147–151.
  • Kirishima A, Hirano M, Sasaki T, et al. Leaching of actinide elements from simulated fuel debris into seawater. J Nucl Sci Technol. 2015;52:1240–1246.
  • Sumita T, Kitagaki T, Takano M, et al. Solidification and re-melting mechanisms of SUS-B4C eutectic mixture. J Nucl Mater. 2021;543:152527.
  • Brissonenneau L, Ikeuchi H, Piluso P, et al. Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants. J Nucl Mater. 2020;528:151860.
  • Takano M, Nishi T, Shirasu N. Characterization of solidified melt among materials of UO2 fuel and B4C control blade. J Nucl Sci Technol. 2014;51:859–875.
  • Pshenichnikov A, Nagae Y, Kurata M. Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test. J Nucl Sci Technol. 2020. DOI:https://doi.org/10.1080/00223131.2020.1856734
  • Kurata M, Shibata H, Sakamoto K, et al. Experimental study on control blade degradation and its modeling. Proc WRFPM 2014. Sendai (Japan); 2014. Paper No. 100079.
  • Ikeuchi H, Yano K, Washiya T. Chemical forms of uranium evaluated by thermodynamic calculation associated with distribution of core materials in the damaged reactor pressure vessel. J Nucl Sci Technol. 2020;57:704–718.
  • De Pablo J, Casas I, Giménez J, et al. Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions. J Nucl Mater. 1996;232:138–145.
  • Miwa S, Amaya M, Tanaka K, et al. Research program for the evaluation of fission product and actinide release behavior, focusing on their chemical forms Position and plan of the research program―. Japan: Japan Atomic Energy Agency; 2013. JAEA-Review 2013-034. [in Japanese].
  • IRID’s summary results of subsidy program (the Second solicitation) for the” Project of Decommissioning and Contaminated Water Management (Development of Technologies for Grasping and Analyzing Properties of Fuel Debris (FY2017))” in the FY2015/16 Supplementary Budget [Released on April 9, 2019]. Available from: https://irid.or.jp/wp-content/uploads/2018/06/20170000_12.pdf [in Japanese].
  • Akers DW, Bart G, Bottomley P, et al. TMI-2 examination results from the OECD/CSNI program. USA: Idaho National Engineering Laboratory EG&G Idaho, Inc; 1992. EGG-OECD-9168 volumes 1, and 2.
  • Tsurikov F, Strizhov VF, Bechta SV, et al. Main results of the MASCA 1 and 2 projects. Russia: Kurchatov Institute; 2007. OECD MASCA project Integrated report.
  • McDeavitt SM, Abraham DP, Park JY. Evaluation of stainless steel–zirconium alloys as high-level nuclear waste forms. J Nucl Mater. 1998;257:21–34.
  • Ebert WL. Testing to evaluate the suitability of waste forms developed for electrometallurgically treated spent Sodium-bonded nuclear fuel for disposal in the Yucca Mountain repository. USA: Argonne National Laboratory; 2005. ANL-05/43.
  • Maeda T, Banda T, Mizuno T, et al. Dissolution behavior of slag in cement-equilibrated aqueous solutions. J Jpn Soc Waste Manage Expert. 2006; 17:271–280 [in Japanese].
  • Gamsjäger H, Bugajski J, Gajda T, et al. Chemical thermodynamics of nickel. Nuclear Energy Agency Data Bank, Organisation for Economic Co-operation and Development, Ed., vol. 6, Chemical Thermodynamics. Amsterdam (The Netherlands): North Holland Elsevier Science Publishers B. V.; 2005.
  • Gayer KH, Garrett AB. The equilibria of nickel hydroxide, Ni(OH)2, in solutions of hydrochloric acid and sodium hydroxide at 25°. J Am Chem Soc. 1949;71:2973–2975.
  • Foote HW. Equilibrium in the systems, nickel chloride, cobalt chloride, cupric chloride–hydrochloric acid–water. J Am Chem Soc. 1923;45:663–667.
  • Rard JA. Isopiestic investigation of water activities of aqueous NiCl2 and CuCl2 solutions and the thermodynamic solubility product of NiCl2·6H2O at 298.15 K. J Chem Eng Data. 1992;37:433–442.
  • Liu X, Millero J. The solubility of iron hydroxide in sodium chloride solutions. Geochim Cosmochim Acta. 1999;63:3487–3497.
  • Gayer KH, Woontner L. The solubility of ferrous hydroxide and ferric hydroxide in acidic and basic media at 25°. J Phys Chem. 1956;60:1569–1571.
  • Ekberg C, Källvenius G, Albinsson Y, et al. Studies on the hydrolytic behavior of zirconium(IV). J Sol Chem. 2004;33:47–79.
  • Sasaki T, Kobayashi T, Tagaki I, et al. Solubility measurement of zirconium(IV) hydrous oxide. Radiochim Acta. 2006;94:489–494.
  • González-Siso MR, Gaona X, Duro L, et al. Thermodynamic model of Ni(II) solubility hydrolysis and complex formation with ISA. Radiochim Acta. 2018;106:31–45.
  • Rai D, Sass BM, Moore DA. Chromium(III) hydrolysis constants and solubility of chromium(III) hydroxide. Inorg Chem. 1987;26:345–349.
  • Rai D, Hess NJ, Rao L, et al. Thermodynamic model for the solubility of Cr(OH)3(am) in concentrated NaOH and NaOH – NaNO3 solutions. J Solution Chem. 2002;31:343–367.
  • Ziemniak SE, Jones ME, Combs KES. Solubility and phase behavior of Cr(III) oxides in alkaline media at elevated temperatures. J Solution Chem. 1998;27:33–66.
  • Das N, Sengupta P, Roychowdhury S, et al. Metallurgical characterizations of Fe–Cr–Ni–Zr base alloys developed for geological disposal of radioactive hulls. J Nucl Mater. 2012;420:559–574.
  • Li C, Zuo R, Li Z, et al. Transmission electron microscopy investigation of Zr2(Fe,Ni) particles incorporated in the oxide film formed on a Zirconium alloy. Thin Solid Films. 2004;461:272–276.
  • Abraham DP, Dietz N. Role of laves intermetallics in nuclear waste disposal. Mater Sci Eng A. 2002;329–331:610–615.
  • Bairi LR, Ningshen S, Mudali K, et al. Microstructural analysis and corrosion behaviour of D9 stainless steel–Zirconium metal waste form alloys. Corr Sci. 2010;52:2291–2302.
  • Das N, Abraham G, Sengupta P, et al. Microstructural analysis and corrosion behavior of zirconium-stainless steel metallic waste form. J Nucl Mater. 2015;467:489–499.

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