Recent knowledge from an experimental investigation on self-leveling behavior of debris bed

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Studies on the self-leveling behavior of debris bed are crucial in the assessment of core-disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR). To clarify the mechanisms of this behavior, several series of experiments were elaborately designed and performed in recent years under the collaboration between Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). This paper presents the recent knowledge obtained from the newly developed large-scale experiments using gas-injection to simulate coolant boiling. Compared to previous investigations, it can cover a much wider range of gas velocities (presently up to a flow rate of around 300L/min). Based on the experimental data obtained, influence of various experimental parameters, including gas flow rate (∼ 300 L/min), water depth (180 mm and 400mm), bed volume (5L, 7L), particle size (2 ∼ 6 mm), particle density (beads of alumina, zirconia and stainless steel) along with particle shape (spherical and irregularly-shaped) on the leveling was checked and compared. In addition, the status of developing empirical model to predict the self-leveling over current setup was also presented. This work, which gives a large palette of favorable data for a better understanding and an improved estimation of CDAs in SFRs, is expected to benefit future analyses and verifications of computer models developed in advanced fast reactor safety analysis codes.

Original languageEnglish
Title of host publicationThermal Hydraulics
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9780791855812
DOIs
Publication statusPublished - Jan 1 2013
Event2013 21st International Conference on Nuclear Engineering, ICONE 2013 - Chengdu, China
Duration: Jul 29 2013Aug 2 2013

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume4

Other

Other2013 21st International Conference on Nuclear Engineering, ICONE 2013
CountryChina
CityChengdu
Period7/29/138/2/13

Fingerprint

Fast reactors
Debris
Core disruptive accidents
Flow rate
Nuclear energy
Zirconia
Coolants
Boiling liquids
Flow of gases
Alumina
Stainless steel
Experiments
Particle size
Sodium
Gases
Water

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Cheng, S., Yamano, H., Suzuki, T., Tobita, Y., Nakamura, Y., Taketa, S., ... Morita, K. (2013). Recent knowledge from an experimental investigation on self-leveling behavior of debris bed. In Thermal Hydraulics (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 4). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE21-15595

Recent knowledge from an experimental investigation on self-leveling behavior of debris bed. / Cheng, Songbai; Yamano, Hidemasa; Suzuki, Tohru; Tobita, Yoshiharu; Nakamura, Yuya; Taketa, Syohei; Nishi, Sinpei; Zhang, Bin; Matsumoto, Tatsuya; Morita, Koji.

Thermal Hydraulics. American Society of Mechanical Engineers (ASME), 2013. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 4).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Cheng, S, Yamano, H, Suzuki, T, Tobita, Y, Nakamura, Y, Taketa, S, Nishi, S, Zhang, B, Matsumoto, T & Morita, K 2013, Recent knowledge from an experimental investigation on self-leveling behavior of debris bed. in Thermal Hydraulics. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 4, American Society of Mechanical Engineers (ASME), 2013 21st International Conference on Nuclear Engineering, ICONE 2013, Chengdu, China, 7/29/13. https://doi.org/10.1115/ICONE21-15595
Cheng S, Yamano H, Suzuki T, Tobita Y, Nakamura Y, Taketa S et al. Recent knowledge from an experimental investigation on self-leveling behavior of debris bed. In Thermal Hydraulics. American Society of Mechanical Engineers (ASME). 2013. (International Conference on Nuclear Engineering, Proceedings, ICONE). https://doi.org/10.1115/ICONE21-15595
Cheng, Songbai ; Yamano, Hidemasa ; Suzuki, Tohru ; Tobita, Yoshiharu ; Nakamura, Yuya ; Taketa, Syohei ; Nishi, Sinpei ; Zhang, Bin ; Matsumoto, Tatsuya ; Morita, Koji. / Recent knowledge from an experimental investigation on self-leveling behavior of debris bed. Thermal Hydraulics. American Society of Mechanical Engineers (ASME), 2013. (International Conference on Nuclear Engineering, Proceedings, ICONE).
@inproceedings{47fa1c3d66db433fa6832ed2d13872f0,
title = "Recent knowledge from an experimental investigation on self-leveling behavior of debris bed",
abstract = "Studies on the self-leveling behavior of debris bed are crucial in the assessment of core-disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR). To clarify the mechanisms of this behavior, several series of experiments were elaborately designed and performed in recent years under the collaboration between Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). This paper presents the recent knowledge obtained from the newly developed large-scale experiments using gas-injection to simulate coolant boiling. Compared to previous investigations, it can cover a much wider range of gas velocities (presently up to a flow rate of around 300L/min). Based on the experimental data obtained, influence of various experimental parameters, including gas flow rate (∼ 300 L/min), water depth (180 mm and 400mm), bed volume (5L, 7L), particle size (2 ∼ 6 mm), particle density (beads of alumina, zirconia and stainless steel) along with particle shape (spherical and irregularly-shaped) on the leveling was checked and compared. In addition, the status of developing empirical model to predict the self-leveling over current setup was also presented. This work, which gives a large palette of favorable data for a better understanding and an improved estimation of CDAs in SFRs, is expected to benefit future analyses and verifications of computer models developed in advanced fast reactor safety analysis codes.",
author = "Songbai Cheng and Hidemasa Yamano and Tohru Suzuki and Yoshiharu Tobita and Yuya Nakamura and Syohei Taketa and Sinpei Nishi and Bin Zhang and Tatsuya Matsumoto and Koji Morita",
year = "2013",
month = "1",
day = "1",
doi = "10.1115/ICONE21-15595",
language = "English",
isbn = "9780791855812",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
publisher = "American Society of Mechanical Engineers (ASME)",
booktitle = "Thermal Hydraulics",

}

TY - GEN

T1 - Recent knowledge from an experimental investigation on self-leveling behavior of debris bed

AU - Cheng, Songbai

AU - Yamano, Hidemasa

AU - Suzuki, Tohru

AU - Tobita, Yoshiharu

AU - Nakamura, Yuya

AU - Taketa, Syohei

AU - Nishi, Sinpei

AU - Zhang, Bin

AU - Matsumoto, Tatsuya

AU - Morita, Koji

PY - 2013/1/1

Y1 - 2013/1/1

N2 - Studies on the self-leveling behavior of debris bed are crucial in the assessment of core-disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR). To clarify the mechanisms of this behavior, several series of experiments were elaborately designed and performed in recent years under the collaboration between Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). This paper presents the recent knowledge obtained from the newly developed large-scale experiments using gas-injection to simulate coolant boiling. Compared to previous investigations, it can cover a much wider range of gas velocities (presently up to a flow rate of around 300L/min). Based on the experimental data obtained, influence of various experimental parameters, including gas flow rate (∼ 300 L/min), water depth (180 mm and 400mm), bed volume (5L, 7L), particle size (2 ∼ 6 mm), particle density (beads of alumina, zirconia and stainless steel) along with particle shape (spherical and irregularly-shaped) on the leveling was checked and compared. In addition, the status of developing empirical model to predict the self-leveling over current setup was also presented. This work, which gives a large palette of favorable data for a better understanding and an improved estimation of CDAs in SFRs, is expected to benefit future analyses and verifications of computer models developed in advanced fast reactor safety analysis codes.

AB - Studies on the self-leveling behavior of debris bed are crucial in the assessment of core-disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR). To clarify the mechanisms of this behavior, several series of experiments were elaborately designed and performed in recent years under the collaboration between Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). This paper presents the recent knowledge obtained from the newly developed large-scale experiments using gas-injection to simulate coolant boiling. Compared to previous investigations, it can cover a much wider range of gas velocities (presently up to a flow rate of around 300L/min). Based on the experimental data obtained, influence of various experimental parameters, including gas flow rate (∼ 300 L/min), water depth (180 mm and 400mm), bed volume (5L, 7L), particle size (2 ∼ 6 mm), particle density (beads of alumina, zirconia and stainless steel) along with particle shape (spherical and irregularly-shaped) on the leveling was checked and compared. In addition, the status of developing empirical model to predict the self-leveling over current setup was also presented. This work, which gives a large palette of favorable data for a better understanding and an improved estimation of CDAs in SFRs, is expected to benefit future analyses and verifications of computer models developed in advanced fast reactor safety analysis codes.

UR - http://www.scopus.com/inward/record.url?scp=84901706098&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84901706098&partnerID=8YFLogxK

U2 - 10.1115/ICONE21-15595

DO - 10.1115/ICONE21-15595

M3 - Conference contribution

AN - SCOPUS:84901706098

SN - 9780791855812

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Thermal Hydraulics

PB - American Society of Mechanical Engineers (ASME)

ER -