Initial relocation behavior of control rod materials in boiling water reactors studied via time-resolved visualization

•Relocation behavior of a control rod is studied via dynamic visualization.•Control rod is simulated by a stainless steel tube filled with B4C powder.•Effect of rod geometry on its initial relocation is examined.•Three relocation modes of the obtained eutectic melt are identified. For the Fukushima...

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Published inNuclear engineering and design Vol. 333; pp. 99 - 114
Main Authors Ueda, Shota, Jo, Byeongnam, Kondo, Masahiro, Erkan, Nejdet, Yajima, Takeshi, Okamoto, Koji
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.07.2018
Elsevier BV
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Abstract •Relocation behavior of a control rod is studied via dynamic visualization.•Control rod is simulated by a stainless steel tube filled with B4C powder.•Effect of rod geometry on its initial relocation is examined.•Three relocation modes of the obtained eutectic melt are identified. For the Fukushima decommissioning, the distribution of boron species in the fuel debris must be determined to assess the risk of recriticality, the debris hardness and thus complicate its successful retrieval. As a result, the relocation behavior of boron carbide (B4C) control rod materials has attracted significant attention. In this work, the influence of the thickness of its stainless steel (SS) clad on the initial relocation behavior of the control rod was investigated. In particular, the initial relocation behavior of the B4C control rod materials was dynamically visualized using a technique previously developed by the authors. To simulate the control rod, a type-304 SS tube filled with B4C powder containing particles with sizes of approximately 20–30 µm was heated to a temperature exceeding its eutectic point (1473 K). The three relocation modes of the obtained eutectic melt corresponded to film formation, droplet formation without collapse and droplet formation with collapse.
AbstractList For the Fukushima decommissioning, the distribution of boron species in the fuel debris must be determined to assess the risk of recriticality, the debris hardness and thus complicate its successful retrieval. As a result, the relocation behavior of boron carbide (B4C) control rod materials has attracted significant attention. In this work, the influence of the thickness of its stainless steel (SS) clad on the initial relocation behavior of the control rod was investigated. In particular, the initial relocation behavior of the B4C control rod materials was dynamically visualized using a technique previously developed by the authors. To simulate the control rod, a type-304 SS tube filled with B4C powder containing particles with sizes of approximately 20–30 µm was heated to a temperature exceeding its eutectic point (1473 K). The three relocation modes of the obtained eutectic melt corresponded to film formation, droplet formation without collapse and droplet formation with collapse.
•Relocation behavior of a control rod is studied via dynamic visualization.•Control rod is simulated by a stainless steel tube filled with B4C powder.•Effect of rod geometry on its initial relocation is examined.•Three relocation modes of the obtained eutectic melt are identified. For the Fukushima decommissioning, the distribution of boron species in the fuel debris must be determined to assess the risk of recriticality, the debris hardness and thus complicate its successful retrieval. As a result, the relocation behavior of boron carbide (B4C) control rod materials has attracted significant attention. In this work, the influence of the thickness of its stainless steel (SS) clad on the initial relocation behavior of the control rod was investigated. In particular, the initial relocation behavior of the B4C control rod materials was dynamically visualized using a technique previously developed by the authors. To simulate the control rod, a type-304 SS tube filled with B4C powder containing particles with sizes of approximately 20–30 µm was heated to a temperature exceeding its eutectic point (1473 K). The three relocation modes of the obtained eutectic melt corresponded to film formation, droplet formation without collapse and droplet formation with collapse.
Author Ueda, Shota
Okamoto, Koji
Jo, Byeongnam
Erkan, Nejdet
Yajima, Takeshi
Kondo, Masahiro
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CitedBy_id crossref_primary_10_1016_j_pnucene_2024_105160
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crossref_primary_10_1016_j_anucene_2022_109462
Cites_doi 10.1299/mel.16-00056
10.1016/j.nucengdes.2009.02.008
10.1016/j.nucengdes.2011.08.031
10.1016/S0022-3115(96)00747-7
10.1016/j.pnucene.2009.09.017
10.1080/00223131.2014.912567
10.1016/j.anucene.2013.09.027
10.1016/S0029-5493(03)00157-2
10.1080/00223131.2016.1209445
10.13182/NT16-10
10.1103/PhysRev.17.273
10.1080/00223131.2015.1011721
10.13182/NT90-A34417
10.13182/NT06-A3721
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Keywords Visualization
Control rod
Boiling water reactor
Severe accident
Eutectic melting
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References Hofmann, Markiewicz, Spino (b0030) 1990; 90
Steinbrück (b0065) 2014; 64
Ueda, Madokoro, Jo, Kondo, Erkan, Okamoto (b0080) 2017; 54
Furuya, Morooka (b0010) 2015
Gauntt, R.O., Gasser, R.D., 1990. Results of the DF-4 BWR control blade-channel box test. In: Prc. Eighteenth Water Reactor Safety Information Meeting, NUREG/CP-0114, vol. 2, pp. 25–40.
Takano, Nishi, Shirasu (b0070) 2014; 51
Ueda, Madokoro, Jo, Kondo, Erkan, Okamoto (b0075) 2016; 2
Haste, Payot, Dominguez, March, Simondi-Teisseire, Steinbrück (b0025) 2012; 246
Washburn (b0085) 1921; 17
Gauntt, R.O., Gasser, R.D., Ott, L.J., 1989. The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box. Sandia National Laboratory, USA, Report NUREG/CR-4671.
Clément, Hanniet-Girault, Repetto, Jacquemain, Jones, Kissane, Von der Hardt (b0005) 2003; 226
Nagase, Gauntt, Naito (b0040) 2017; 196
Ikeuchi, H., Piluso, P., Fouquart, P., Excoffier, E., David, C., Brackx, E., 2017. Study on the distribution of boron in the in-vessel fuel debris in conditions close to Fukushima Daiichi Nuclear Power Station Unit 2. The 8th European Review Meeting on Severe Accident Research (ERMSAR) 2017, Warsaw, Poland.
Nagase, Uetsuka, Otomo (b0045) 1997; 245
Girault, Fiche, Bujan, Dienstbier (b0020) 2009; 239
Shibata, Sakamoto, Ouchi, Kurata (b0060) 2015; 52
Sepold, Schanz, Steinbrück, Stuckert, Miassoedov, Palagin, Veshchunov (b0055) 2006; 154
Repetto, De Luze, Seiler, Trambauer, Austregesilo, Birchley, Ederli, Lamy, Maliverney, Drath, Hollands (b0050) 2010; 52
Washburn (10.1016/j.nucengdes.2018.04.006_b0085) 1921; 17
Repetto (10.1016/j.nucengdes.2018.04.006_b0050) 2010; 52
Clément (10.1016/j.nucengdes.2018.04.006_b0005) 2003; 226
10.1016/j.nucengdes.2018.04.006_b9000
Nagase (10.1016/j.nucengdes.2018.04.006_b0045) 1997; 245
Sepold (10.1016/j.nucengdes.2018.04.006_b0055) 2006; 154
Takano (10.1016/j.nucengdes.2018.04.006_b0070) 2014; 51
Girault (10.1016/j.nucengdes.2018.04.006_b0020) 2009; 239
Steinbrück (10.1016/j.nucengdes.2018.04.006_b0065) 2014; 64
Hofmann (10.1016/j.nucengdes.2018.04.006_b0030) 1990; 90
Furuya (10.1016/j.nucengdes.2018.04.006_b0010) 2015
Ueda (10.1016/j.nucengdes.2018.04.006_b0075) 2016; 2
10.1016/j.nucengdes.2018.04.006_b0015
Haste (10.1016/j.nucengdes.2018.04.006_b0025) 2012; 246
10.1016/j.nucengdes.2018.04.006_b0035
Nagase (10.1016/j.nucengdes.2018.04.006_b0040) 2017; 196
Ueda (10.1016/j.nucengdes.2018.04.006_b0080) 2017; 54
Shibata (10.1016/j.nucengdes.2018.04.006_b0060) 2015; 52
References_xml – year: 2015
  ident: b0010
  article-title: Visual Observation of Natural Convection due to Eutectic Melting of Stainless Steel and Boron Carbide and Three-Dimensional Raman Spectrometry
  contributor:
    fullname: Morooka
– volume: 246
  start-page: 147
  year: 2012
  end-page: 156
  ident: b0025
  article-title: Study of boron behavior in the primary circuit of water reactors under severe accident conditions: a comparison of Phebus FPT3 results with other recent integral and separate-effects data
  publication-title: Nucl. Eng. Des
  contributor:
    fullname: Steinbrück
– volume: 196
  start-page: 499
  year: 2017
  end-page: 510
  ident: b0040
  article-title: Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi nuclear power station
  publication-title: Nucl. Technol
  contributor:
    fullname: Naito
– volume: 90
  start-page: 226
  year: 1990
  end-page: 244
  ident: b0030
  article-title: Reaction behavior of B4C absorber material with stainless steel and zircaloy in severe light water reactor accidents
  publication-title: Nucl. Technol.
  contributor:
    fullname: Spino
– volume: 245
  start-page: 52
  year: 1997
  end-page: 59
  ident: b0045
  article-title: Chemical interactions between B4C and stainless steel at high temperatures
  publication-title: J. Nucl. Mater.
  contributor:
    fullname: Otomo
– volume: 17
  start-page: 273
  year: 1921
  ident: b0085
  article-title: The dynamics of capillary flow
  publication-title: Phys. Rev.
  contributor:
    fullname: Washburn
– volume: 54
  start-page: 81
  year: 2017
  end-page: 88
  ident: b0080
  article-title: Dynamic visualization of eutectic reaction between boron carbide and stainless steel
  publication-title: J. Nucl. Sci. Technol.
  contributor:
    fullname: Okamoto
– volume: 64
  start-page: 43
  year: 2014
  end-page: 49
  ident: b0065
  article-title: Influence of boron carbide on core degradation during severe accidents in LWRs
  publication-title: Ann. Nucl. Energy
  contributor:
    fullname: Steinbrück
– volume: 226
  start-page: 582
  year: 2003
  ident: b0005
  article-title: LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT0
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Von der Hardt
– volume: 52
  start-page: 37
  year: 2010
  end-page: 45
  ident: b0050
  article-title: B4C oxidation modelling in severe accident codes: applications to PHEBUS and QUENCH experiments
  publication-title: Prog. Nucl. Energy
  contributor:
    fullname: Hollands
– volume: 52
  start-page: 1313
  year: 2015
  end-page: 1317
  ident: b0060
  article-title: Chemical interaction between granular B4C and 304L-type stainless steel materials used in BWRs in Japan
  publication-title: J. Nucl. Sci. Technol.
  contributor:
    fullname: Kurata
– volume: 154
  start-page: 107
  year: 2006
  end-page: 116
  ident: b0055
  article-title: Results of the QUENCH-09 experiment compared to QUENCH-07 with incorporation of B4C absorber
  publication-title: Nucl. Technol.
  contributor:
    fullname: Veshchunov
– volume: 239
  start-page: 1162
  year: 2009
  end-page: 1170
  ident: b0020
  article-title: Towards a better understanding of iodine chemistry in RCS of nuclear reactors
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Dienstbier
– volume: 51
  start-page: 859
  year: 2014
  end-page: 875
  ident: b0070
  article-title: Characterization of solidified melt among materials of UO2 fuel and B4C control blade
  publication-title: J. Nucl. Sci. Technol.
  contributor:
    fullname: Shirasu
– volume: 2
  start-page: 16
  year: 2016
  end-page: 00056
  ident: b0075
  article-title: Time-resolved visualization technique for eutectic reaction between boron carbide and stainless steel at high temperatures
  publication-title: Mech. Eng. Lett
  contributor:
    fullname: Okamoto
– volume: 2
  start-page: 16
  year: 2016
  ident: 10.1016/j.nucengdes.2018.04.006_b0075
  article-title: Time-resolved visualization technique for eutectic reaction between boron carbide and stainless steel at high temperatures
  publication-title: Mech. Eng. Lett.
  doi: 10.1299/mel.16-00056
  contributor:
    fullname: Ueda
– volume: 239
  start-page: 1162
  year: 2009
  ident: 10.1016/j.nucengdes.2018.04.006_b0020
  article-title: Towards a better understanding of iodine chemistry in RCS of nuclear reactors
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/j.nucengdes.2009.02.008
  contributor:
    fullname: Girault
– ident: 10.1016/j.nucengdes.2018.04.006_b0015
– volume: 246
  start-page: 147
  year: 2012
  ident: 10.1016/j.nucengdes.2018.04.006_b0025
  article-title: Study of boron behavior in the primary circuit of water reactors under severe accident conditions: a comparison of Phebus FPT3 results with other recent integral and separate-effects data
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/j.nucengdes.2011.08.031
  contributor:
    fullname: Haste
– volume: 245
  start-page: 52
  year: 1997
  ident: 10.1016/j.nucengdes.2018.04.006_b0045
  article-title: Chemical interactions between B4C and stainless steel at high temperatures
  publication-title: J. Nucl. Mater.
  doi: 10.1016/S0022-3115(96)00747-7
  contributor:
    fullname: Nagase
– volume: 52
  start-page: 37
  year: 2010
  ident: 10.1016/j.nucengdes.2018.04.006_b0050
  article-title: B4C oxidation modelling in severe accident codes: applications to PHEBUS and QUENCH experiments
  publication-title: Prog. Nucl. Energy
  doi: 10.1016/j.pnucene.2009.09.017
  contributor:
    fullname: Repetto
– volume: 51
  start-page: 859
  year: 2014
  ident: 10.1016/j.nucengdes.2018.04.006_b0070
  article-title: Characterization of solidified melt among materials of UO2 fuel and B4C control blade
  publication-title: J. Nucl. Sci. Technol.
  doi: 10.1080/00223131.2014.912567
  contributor:
    fullname: Takano
– volume: 64
  start-page: 43
  year: 2014
  ident: 10.1016/j.nucengdes.2018.04.006_b0065
  article-title: Influence of boron carbide on core degradation during severe accidents in LWRs
  publication-title: Ann. Nucl. Energy
  doi: 10.1016/j.anucene.2013.09.027
  contributor:
    fullname: Steinbrück
– volume: 226
  start-page: 582
  year: 2003
  ident: 10.1016/j.nucengdes.2018.04.006_b0005
  article-title: LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT0
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/S0029-5493(03)00157-2
  contributor:
    fullname: Clément
– volume: 54
  start-page: 81
  year: 2017
  ident: 10.1016/j.nucengdes.2018.04.006_b0080
  article-title: Dynamic visualization of eutectic reaction between boron carbide and stainless steel
  publication-title: J. Nucl. Sci. Technol.
  doi: 10.1080/00223131.2016.1209445
  contributor:
    fullname: Ueda
– ident: 10.1016/j.nucengdes.2018.04.006_b0035
– volume: 196
  start-page: 499
  year: 2017
  ident: 10.1016/j.nucengdes.2018.04.006_b0040
  article-title: Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi nuclear power station
  publication-title: Nucl. Technol.
  doi: 10.13182/NT16-10
  contributor:
    fullname: Nagase
– volume: 17
  start-page: 273
  year: 1921
  ident: 10.1016/j.nucengdes.2018.04.006_b0085
  article-title: The dynamics of capillary flow
  publication-title: Phys. Rev.
  doi: 10.1103/PhysRev.17.273
  contributor:
    fullname: Washburn
– volume: 52
  start-page: 1313
  year: 2015
  ident: 10.1016/j.nucengdes.2018.04.006_b0060
  article-title: Chemical interaction between granular B4C and 304L-type stainless steel materials used in BWRs in Japan
  publication-title: J. Nucl. Sci. Technol.
  doi: 10.1080/00223131.2015.1011721
  contributor:
    fullname: Shibata
– volume: 90
  start-page: 226
  year: 1990
  ident: 10.1016/j.nucengdes.2018.04.006_b0030
  article-title: Reaction behavior of B4C absorber material with stainless steel and zircaloy in severe light water reactor accidents
  publication-title: Nucl. Technol.
  doi: 10.13182/NT90-A34417
  contributor:
    fullname: Hofmann
– year: 2015
  ident: 10.1016/j.nucengdes.2018.04.006_b0010
  contributor:
    fullname: Furuya
– ident: 10.1016/j.nucengdes.2018.04.006_b9000
– volume: 154
  start-page: 107
  year: 2006
  ident: 10.1016/j.nucengdes.2018.04.006_b0055
  article-title: Results of the QUENCH-09 experiment compared to QUENCH-07 with incorporation of B4C absorber
  publication-title: Nucl. Technol.
  doi: 10.13182/NT06-A3721
  contributor:
    fullname: Sepold
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Snippet •Relocation behavior of a control rod is studied via dynamic visualization.•Control rod is simulated by a stainless steel tube filled with B4C powder.•Effect...
For the Fukushima decommissioning, the distribution of boron species in the fuel debris must be determined to assess the risk of recriticality, the debris...
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elsevier
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StartPage 99
SubjectTerms Boiling water reactor
Boiling water reactors
Boron
Boron carbide
Collapse
Control rod
Control rods
Debris
Eutectic melting
Kinetics
Nuclear energy
Nuclear engineering
Nuclear fuels
Nuclear reactors
Powder
Reactors
Relocation
Severe accident
Stainless steel
Thermodynamics
Visualization
Title Initial relocation behavior of control rod materials in boiling water reactors studied via time-resolved visualization
URI https://dx.doi.org/10.1016/j.nucengdes.2018.04.006
https://www.proquest.com/docview/2069502286/abstract/
Volume 333
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