Backward analysis of U-bearing particles from the Fukushima Daiichi Nuclear Power Station using the Scheil–Gulliver solidification model of the U–Zr–Fe–O system
•Crystal structure and U–Zr–Fe ratio of U-bearing particle reflects debris state.•Fe-addition promoted separation of solid solution to U-rich and U-depleted fluorite.•Solid phases without Fe can be formed even from Fe-containing liquid states.•U-bearing particles could originate from liquid above 18...
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Published in | Journal of nuclear materials Vol. 614; p. 155892 |
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Main Authors | , , |
Format | Journal Article |
Language | English |
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Elsevier B.V
01.08.2025
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ISSN | 0022-3115 |
DOI | 10.1016/j.jnucmat.2025.155892 |
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Abstract | •Crystal structure and U–Zr–Fe ratio of U-bearing particle reflects debris state.•Fe-addition promoted separation of solid solution to U-rich and U-depleted fluorite.•Solid phases without Fe can be formed even from Fe-containing liquid states.•U-bearing particles could originate from liquid above 1800 K during accidents.
For the decommissioning of the Fukushima Daiichi Nuclear Power Station (FDNPS), a methodology is needed for evaluating the chemical conditions where fuel debris formed during the accident, which is also a starting point for estimating current in-vessel state. The crystal structures and compositions of fuel debris provide information about their formation mechanisms and solidification paths. In this study, we performed Scheil–Gulliver solidification simulation for a wide range of U–Zr–Fe–O compositions (1829 points), obtaining theoretical phase relations in the solidified state. Then, we developed a method of backward estimating possible liquid-state compositions and demonstrated this method on six samples taken from the FDNPS (so-called as "U-bearing particles") by comparing their morphologies and compositions with their theoretical counterparts in the solidified state. Results showed that all samples were likely formed from liquids with a wide range of oxygen to metals ratio from 0.14 to 1.70, and fluorite oxide without Fe could form even from Fe-containing compositions. Introducing Cr into the analysis with the U–Zr–Fe–Cr–O system is expected to improve this method, enabling the inclusion of Cr-rich spinel formation in the search conditions in future work. |
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AbstractList | •Crystal structure and U–Zr–Fe ratio of U-bearing particle reflects debris state.•Fe-addition promoted separation of solid solution to U-rich and U-depleted fluorite.•Solid phases without Fe can be formed even from Fe-containing liquid states.•U-bearing particles could originate from liquid above 1800 K during accidents.
For the decommissioning of the Fukushima Daiichi Nuclear Power Station (FDNPS), a methodology is needed for evaluating the chemical conditions where fuel debris formed during the accident, which is also a starting point for estimating current in-vessel state. The crystal structures and compositions of fuel debris provide information about their formation mechanisms and solidification paths. In this study, we performed Scheil–Gulliver solidification simulation for a wide range of U–Zr–Fe–O compositions (1829 points), obtaining theoretical phase relations in the solidified state. Then, we developed a method of backward estimating possible liquid-state compositions and demonstrated this method on six samples taken from the FDNPS (so-called as "U-bearing particles") by comparing their morphologies and compositions with their theoretical counterparts in the solidified state. Results showed that all samples were likely formed from liquids with a wide range of oxygen to metals ratio from 0.14 to 1.70, and fluorite oxide without Fe could form even from Fe-containing compositions. Introducing Cr into the analysis with the U–Zr–Fe–Cr–O system is expected to improve this method, enabling the inclusion of Cr-rich spinel formation in the search conditions in future work. |
ArticleNumber | 155892 |
Author | Hirai, Mutsumi Itoh, Ayumi Mizokami, Masato |
Author_xml | – sequence: 1 givenname: Ayumi orcidid: 0000-0001-7460-0613 surname: Itoh fullname: Itoh, Ayumi email: itoh.a.ae@m.titech.ac.jp organization: Laboratory for Zero-Carbon Energy, Institute of Science Technology, 2-12-1, Ookayama, Meguro-ku, Tokyo 152-8550, Japan – sequence: 2 givenname: Masato orcidid: 0000-0003-0241-7814 surname: Mizokami fullname: Mizokami, Masato organization: Tokyo Electric Power Company Holdings, Inc, 1-1-3 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100-8560, Japan – sequence: 3 givenname: Mutsumi surname: Hirai fullname: Hirai, Mutsumi organization: Tokyo Electric Power Company Holdings, Inc, 1-1-3 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100-8560, Japan |
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Cites_doi | 10.1016/j.jnucmat.2005.04.052 10.1080/00223131.2022.2040393 10.1080/00223131.2014.912567 10.1016/j.jnucmat.2010.02.022 10.1016/j.jnucmat.2024.155456 10.1016/j.nucengdes.2024.112957 10.1016/j.calphad.2015.01.002 10.13182/NT89-A27643 10.1016/j.calphad.2020.102212 |
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Keywords | Backward estimation of fuel debris Scheil–Gulliver Nearest-neighbor search U-bearing particle Fukushima Daiichi Nuclear Power Station |
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References | Steinbrück (bib0017) 2010; 400 Piluso, Trillon, Journeau (bib0012) 2005; 344 Geiger, E.; Benes, O.; Vigier, J.; Boboridis, K.; Robba, D.; Colle, J.; Cremer, B.; Ernstberger, M.; Poeml, P.; Himbert, J.; Gardeur, S.; Lajarge, P.; Popa, K.; Boshoven, C.; Vlahovic, L.; Wiss, T.; Piro, M.H.; Konings, R., Experimental validation of the TAF-ID: High temperature behaviour of simulated Ex-vessel corium and MOX-Lanthanides (Ce, Gd, La, Nd), Publications Office of the European Union, Luxembourg, 2023 Ohgi, Nagae, Kurata (bib0005) 2022; 2022 Thermo-Calc software, The TC-python API programmer guide 2024b (accessed 21 June 2024), (2024). Trillon, G., Analysis of the corium phases by X-ray diffraction (CEA-R–6045), 2004. Nishihara, K.; Iwamoto, H.; Suyama, K., Estimation of fuel compositions in Fukushima-Daiichi Nuclear Power Plant (JAEA-Data/Code-2012-018), Japan Atomic Energy Agency, Ibaraki, 2012 . Schaffnit, Stallybrass, Konrad, Stein, Weinberg (bib0010) 2015; 48 Brown, McIntyre, Gräslund (bib0014) 1989; 87 Lewis, Thompson, Iglesias (bib0019) 2012 Ikeuchi, H.; Sasaki, S.; Onishi, T.; Nakayoshi, A.; Arai, Y.; Sato, T.; Ohgi, H.; Sekio, Y; Yamaguchi, Y.; Morishita, K.; Maeda, K., Analysis of deposits inside the reactor at fukushima daiichi nuclear power station (JAEA-Data/Code-2023-005), Japan Atomic Energy Agency, Ibaraki, 2023. Inoue, Itoh, Mizokami, Hirai (bib0018) 2025; 603 Gulliver (bib0008) 1913; 9 Takano, Nishi, Shirasu (bib0016) 2014; 51 Kurata, Okuzumi, Nakayoshi, Ikeuchi, Koyama (bib0004) 2022; 59 Tokyo Electric Power Co. Ltd., Sample analysis to understand the accident situation (Attachment 5), 2022. Breeden, Poschmann, Piro (bib0006) 2024; 419 Nakayoshi, Mitsugi, Sasaki, Maeda (bib0002) 2021 (accessed May 4, 2024). Gueneau, Dupin, Kjellqvist, Geiger, Kurata, Goss, Quaini, Hania, Smith, Piro, Besmann, Turchi, Dumas, Welland, Ogata, Lee, Kennedy, Adkins, Bankhead, Costa (bib0007) 2021; 72 Thermo-Calc software, Thermo-calc documentation Set, version 2024b (accessed 21 June 2024), (2024). 10.1016/j.jnucmat.2025.155892_bib0009 Piluso (10.1016/j.jnucmat.2025.155892_bib0012) 2005; 344 Nakayoshi (10.1016/j.jnucmat.2025.155892_bib0002) 2021 Breeden (10.1016/j.jnucmat.2025.155892_bib0006) 2024; 419 Gueneau (10.1016/j.jnucmat.2025.155892_bib0007) 2021; 72 Steinbrück (10.1016/j.jnucmat.2025.155892_bib0017) 2010; 400 Brown (10.1016/j.jnucmat.2025.155892_bib0014) 1989; 87 Inoue (10.1016/j.jnucmat.2025.155892_bib0018) 2025; 603 10.1016/j.jnucmat.2025.155892_bib0020 10.1016/j.jnucmat.2025.155892_bib0013 Lewis (10.1016/j.jnucmat.2025.155892_bib0019) 2012 10.1016/j.jnucmat.2025.155892_bib0001 Ohgi (10.1016/j.jnucmat.2025.155892_bib0005) 2022; 2022 Schaffnit (10.1016/j.jnucmat.2025.155892_bib0010) 2015; 48 Kurata (10.1016/j.jnucmat.2025.155892_bib0004) 2022; 59 10.1016/j.jnucmat.2025.155892_bib0011 Gulliver (10.1016/j.jnucmat.2025.155892_bib0008) 1913; 9 10.1016/j.jnucmat.2025.155892_bib0015 10.1016/j.jnucmat.2025.155892_bib0003 Takano (10.1016/j.jnucmat.2025.155892_bib0016) 2014; 51 |
References_xml | – volume: 344 start-page: 259 year: 2005 end-page: 264 ident: bib0012 article-title: The UO2–ZrO2 system at high temperature (T >2000K): importance of the meta-stable phases under severe accident conditions publication-title: J. Nucl. Mater. – volume: 51 start-page: 859 year: 2014 end-page: 875 ident: bib0016 article-title: Characterization of solidified melt among materials of UO2fuel and B4C control blade publication-title: J. Nucl. Sci. Technol. – year: 2021 ident: bib0002 article-title: Analysis of deposits inside the reactor at Fukushima Daiichi Nuclear Power Station (JAEA-Data/Code-2021-011) – volume: 87 start-page: 137 year: 1989 end-page: 145 ident: bib0014 article-title: Analysis of crystalline phases in core bore materials from three mile island unit 2 publication-title: Nucl. Technol. – volume: 59 start-page: 807 year: 2022 end-page: 834 ident: bib0004 article-title: Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS) publication-title: J. Nucl. Sci. Technol. – volume: 400 start-page: 138 year: 2010 end-page: 150 ident: bib0017 article-title: Degradation and oxidation of B4C control rod segments at high temperatures publication-title: J. Nucl. Mater. – reference: Ikeuchi, H.; Sasaki, S.; Onishi, T.; Nakayoshi, A.; Arai, Y.; Sato, T.; Ohgi, H.; Sekio, Y; Yamaguchi, Y.; Morishita, K.; Maeda, K., Analysis of deposits inside the reactor at fukushima daiichi nuclear power station (JAEA-Data/Code-2023-005), Japan Atomic Energy Agency, Ibaraki, 2023. – volume: 603 year: 2025 ident: bib0018 article-title: Evaluation of boron evaporation kinetics from stainless-steel–B4C alloy during steam oxidation at high temperatures publication-title: J. Nucl. Mater. – volume: 48 start-page: 184 year: 2015 end-page: 188 ident: bib0010 article-title: A Scheil–Gulliver model dedicated to the solidification of steel publication-title: Calphad – volume: 2022 start-page: 1066 year: 2022 ident: bib0005 article-title: Thermodynamic evaluation on solidification path for U-Zr-Fe-O corium publication-title: Proceedings of the International Topical Workshop on Fukushima Decommissioning Research – reference: Nishihara, K.; Iwamoto, H.; Suyama, K., Estimation of fuel compositions in Fukushima-Daiichi Nuclear Power Plant (JAEA-Data/Code-2012-018), Japan Atomic Energy Agency, Ibaraki, 2012, – reference: . – reference: Thermo-Calc software, Thermo-calc documentation Set, version 2024b (accessed 21 June 2024), (2024). – reference: Thermo-Calc software, The TC-python API programmer guide 2024b (accessed 21 June 2024), (2024). – volume: 9 start-page: 120 year: 1913 end-page: 157 ident: bib0008 article-title: The quantitative effect of rapid cooling upon the constitution of binary alloys publication-title: J. Inst. Met – volume: 419 year: 2024 ident: bib0006 article-title: Using MELCOR with enhanced predictive capabilities via thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl publication-title: Nucl. Eng. Des. – reference: (accessed May 4, 2024). – volume: 72 year: 2021 ident: bib0007 article-title: Calphad TAF-ID : an international thermodynamic database for nuclear fuels applications publication-title: Calphad – reference: Trillon, G., Analysis of the corium phases by X-ray diffraction (CEA-R–6045), 2004. – start-page: 515 year: 2012 end-page: 546 ident: bib0019 article-title: 2.20-fission product chemistry in oxide fuels publication-title: Comprehensive Nuclear Materials – reference: Tokyo Electric Power Co. Ltd., Sample analysis to understand the accident situation (Attachment 5), 2022. – reference: Geiger, E.; Benes, O.; Vigier, J.; Boboridis, K.; Robba, D.; Colle, J.; Cremer, B.; Ernstberger, M.; Poeml, P.; Himbert, J.; Gardeur, S.; Lajarge, P.; Popa, K.; Boshoven, C.; Vlahovic, L.; Wiss, T.; Piro, M.H.; Konings, R., Experimental validation of the TAF-ID: High temperature behaviour of simulated Ex-vessel corium and MOX-Lanthanides (Ce, Gd, La, Nd), Publications Office of the European Union, Luxembourg, 2023, – ident: 10.1016/j.jnucmat.2025.155892_bib0003 – ident: 10.1016/j.jnucmat.2025.155892_bib0001 – volume: 344 start-page: 259 year: 2005 ident: 10.1016/j.jnucmat.2025.155892_bib0012 article-title: The UO2–ZrO2 system at high temperature (T >2000K): importance of the meta-stable phases under severe accident conditions publication-title: J. Nucl. Mater. doi: 10.1016/j.jnucmat.2005.04.052 – volume: 59 start-page: 807 year: 2022 ident: 10.1016/j.jnucmat.2025.155892_bib0004 article-title: Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS) publication-title: J. Nucl. Sci. Technol. doi: 10.1080/00223131.2022.2040393 – volume: 51 start-page: 859 year: 2014 ident: 10.1016/j.jnucmat.2025.155892_bib0016 article-title: Characterization of solidified melt among materials of UO2fuel and B4C control blade publication-title: J. Nucl. Sci. Technol. doi: 10.1080/00223131.2014.912567 – volume: 400 start-page: 138 year: 2010 ident: 10.1016/j.jnucmat.2025.155892_bib0017 article-title: Degradation and oxidation of B4C control rod segments at high temperatures publication-title: J. Nucl. Mater. doi: 10.1016/j.jnucmat.2010.02.022 – ident: 10.1016/j.jnucmat.2025.155892_bib0020 – year: 2021 ident: 10.1016/j.jnucmat.2025.155892_bib0002 article-title: Analysis of deposits inside the reactor at Fukushima Daiichi Nuclear Power Station (JAEA-Data/Code-2021-011) – ident: 10.1016/j.jnucmat.2025.155892_bib0009 – ident: 10.1016/j.jnucmat.2025.155892_bib0015 – volume: 9 start-page: 120 year: 1913 ident: 10.1016/j.jnucmat.2025.155892_bib0008 article-title: The quantitative effect of rapid cooling upon the constitution of binary alloys publication-title: J. Inst. Met – volume: 603 year: 2025 ident: 10.1016/j.jnucmat.2025.155892_bib0018 article-title: Evaluation of boron evaporation kinetics from stainless-steel–B4C alloy during steam oxidation at high temperatures publication-title: J. Nucl. Mater. doi: 10.1016/j.jnucmat.2024.155456 – volume: 419 year: 2024 ident: 10.1016/j.jnucmat.2025.155892_bib0006 article-title: Using MELCOR with enhanced predictive capabilities via thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl publication-title: Nucl. Eng. Des. doi: 10.1016/j.nucengdes.2024.112957 – volume: 2022 start-page: 1066 year: 2022 ident: 10.1016/j.jnucmat.2025.155892_bib0005 article-title: Thermodynamic evaluation on solidification path for U-Zr-Fe-O corium – volume: 48 start-page: 184 year: 2015 ident: 10.1016/j.jnucmat.2025.155892_bib0010 article-title: A Scheil–Gulliver model dedicated to the solidification of steel publication-title: Calphad doi: 10.1016/j.calphad.2015.01.002 – ident: 10.1016/j.jnucmat.2025.155892_bib0011 – start-page: 515 year: 2012 ident: 10.1016/j.jnucmat.2025.155892_bib0019 article-title: 2.20-fission product chemistry in oxide fuels – ident: 10.1016/j.jnucmat.2025.155892_bib0013 – volume: 87 start-page: 137 year: 1989 ident: 10.1016/j.jnucmat.2025.155892_bib0014 article-title: Analysis of crystalline phases in core bore materials from three mile island unit 2 publication-title: Nucl. Technol. doi: 10.13182/NT89-A27643 – volume: 72 year: 2021 ident: 10.1016/j.jnucmat.2025.155892_bib0007 article-title: Calphad TAF-ID : an international thermodynamic database for nuclear fuels applications publication-title: Calphad doi: 10.1016/j.calphad.2020.102212 |
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SubjectTerms | Backward estimation of fuel debris Fukushima Daiichi Nuclear Power Station Nearest-neighbor search Scheil–Gulliver U-bearing particle |
Title | Backward analysis of U-bearing particles from the Fukushima Daiichi Nuclear Power Station using the Scheil–Gulliver solidification model of the U–Zr–Fe–O system |
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