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Development of approaches to simulate fuel rod destruction with different fuel type. / Usov, Eduard; Pribaturin, Nikolay; Chukhno, Vladimir et al.

Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors. American Society of Mechanical Engineers(ASME), 2020. V002T08A031 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › Research › peer-review

Harvard

Usov, E, Pribaturin, N, Chukhno, V, Klimonov, I, Butov, A, Kudashov, I, Gafiyatullin, A & Lobanov, P 2020, Development of approaches to simulate fuel rod destruction with different fuel type. in Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors., V002T08A031, International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 2, American Society of Mechanical Engineers(ASME), 2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference, Virtual, Online, 04.04.2020. https://doi.org/10.1115/ICONE2020-16326

APA

Usov, E., Pribaturin, N., Chukhno, V., Klimonov, I., Butov, A., Kudashov, I., Gafiyatullin, A., & Lobanov, P. (2020). Development of approaches to simulate fuel rod destruction with different fuel type. In Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors [V002T08A031] (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2). American Society of Mechanical Engineers(ASME). https://doi.org/10.1115/ICONE2020-16326

Vancouver

Usov E, Pribaturin N, Chukhno V, Klimonov I, Butov A, Kudashov I et al. Development of approaches to simulate fuel rod destruction with different fuel type. In Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors. American Society of Mechanical Engineers(ASME). 2020. V002T08A031. (International Conference on Nuclear Engineering, Proceedings, ICONE). doi: 10.1115/ICONE2020-16326

Author

Usov, Eduard ; Pribaturin, Nikolay ; Chukhno, Vladimir et al. / Development of approaches to simulate fuel rod destruction with different fuel type. Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors. American Society of Mechanical Engineers(ASME), 2020. (International Conference on Nuclear Engineering, Proceedings, ICONE).

BibTeX

@inproceedings{7fbe700cb2f24d7cb126abb7588f27db,
title = "Development of approaches to simulate fuel rod destruction with different fuel type",
abstract = "Due to the revival of interest to the development of fast reactors cooled by liquid metals, the problem of carrying out theoretical research in support of their safety is actual. A detailed calculation of all stages of the accident from the beginning to the end requires knowledge of the laws for modeling physical processes occurring in the reactor in an emergency. The most serious are accidents with the destruction of the core. Simulation of severe accident in nuclear reactor is the key element in safety analysis of nuclear power plants. Destruction of fuel rods is one of the most important processes that should be calculated during core degradation. For different type of fuels the mechanism of the degradation are different too. For example, oxide and metallic fuels usually melt congruently at high temperature, but nitride fuel dissociates. The main objective of the proposed research is developing of models and numerical algorithms for calculation fuel rods destruction with oxide, metallic and nitride fuels. The models of the destruction processes and some calculation results are presented in the paper. The processes are investigated for the first phase of severe accidents covering the period from the onset of fuel-rod melting to the melt escape from the core center.",
keywords = "Cladding, Films, Fuel pin degradation, Melt, Metallic fuel, Nitride fuel, Oxide fuel",
author = "Eduard Usov and Nikolay Pribaturin and Vladimir Chukhno and Ilya Klimonov and Anton Butov and Ivan Kudashov and Albert Gafiyatullin and Pavel Lobanov",
note = "Funding Information: The work was performed at support of the projects funded by the Russian Science Foundation (RSF No. 18-79-10013). Publisher Copyright: Copyright {\textcopyright} 2020 ASME Copyright: Copyright 2020 Elsevier B.V., All rights reserved.; 2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference ; Conference date: 04-04-2020 Through 05-04-2020",
year = "2020",
doi = "10.1115/ICONE2020-16326",
language = "English",
isbn = "9784888982566",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
publisher = "American Society of Mechanical Engineers(ASME)",
booktitle = "Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors",
address = "United States",

}

RIS

TY - GEN

T1 - Development of approaches to simulate fuel rod destruction with different fuel type

AU - Usov, Eduard

AU - Pribaturin, Nikolay

AU - Chukhno, Vladimir

AU - Klimonov, Ilya

AU - Butov, Anton

AU - Kudashov, Ivan

AU - Gafiyatullin, Albert

AU - Lobanov, Pavel

N1 - Funding Information: The work was performed at support of the projects funded by the Russian Science Foundation (RSF No. 18-79-10013). Publisher Copyright: Copyright © 2020 ASME Copyright: Copyright 2020 Elsevier B.V., All rights reserved.

PY - 2020

Y1 - 2020

N2 - Due to the revival of interest to the development of fast reactors cooled by liquid metals, the problem of carrying out theoretical research in support of their safety is actual. A detailed calculation of all stages of the accident from the beginning to the end requires knowledge of the laws for modeling physical processes occurring in the reactor in an emergency. The most serious are accidents with the destruction of the core. Simulation of severe accident in nuclear reactor is the key element in safety analysis of nuclear power plants. Destruction of fuel rods is one of the most important processes that should be calculated during core degradation. For different type of fuels the mechanism of the degradation are different too. For example, oxide and metallic fuels usually melt congruently at high temperature, but nitride fuel dissociates. The main objective of the proposed research is developing of models and numerical algorithms for calculation fuel rods destruction with oxide, metallic and nitride fuels. The models of the destruction processes and some calculation results are presented in the paper. The processes are investigated for the first phase of severe accidents covering the period from the onset of fuel-rod melting to the melt escape from the core center.

AB - Due to the revival of interest to the development of fast reactors cooled by liquid metals, the problem of carrying out theoretical research in support of their safety is actual. A detailed calculation of all stages of the accident from the beginning to the end requires knowledge of the laws for modeling physical processes occurring in the reactor in an emergency. The most serious are accidents with the destruction of the core. Simulation of severe accident in nuclear reactor is the key element in safety analysis of nuclear power plants. Destruction of fuel rods is one of the most important processes that should be calculated during core degradation. For different type of fuels the mechanism of the degradation are different too. For example, oxide and metallic fuels usually melt congruently at high temperature, but nitride fuel dissociates. The main objective of the proposed research is developing of models and numerical algorithms for calculation fuel rods destruction with oxide, metallic and nitride fuels. The models of the destruction processes and some calculation results are presented in the paper. The processes are investigated for the first phase of severe accidents covering the period from the onset of fuel-rod melting to the melt escape from the core center.

KW - Cladding

KW - Films

KW - Fuel pin degradation

KW - Melt

KW - Metallic fuel

KW - Nitride fuel

KW - Oxide fuel

UR - http://www.scopus.com/inward/record.url?scp=85095455219&partnerID=8YFLogxK

U2 - 10.1115/ICONE2020-16326

DO - 10.1115/ICONE2020-16326

M3 - Conference contribution

AN - SCOPUS:85095455219

SN - 9784888982566

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors

PB - American Society of Mechanical Engineers(ASME)

T2 - 2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

Y2 - 4 April 2020 through 5 April 2020

ER -

ID: 25993145