Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor

Kelsingazina, Ruziya; Vityuk, Vladimir; Vurim, Alexander; Vityuk, Galina; Mukhamedov, Nurzhan; Tikhomirov, Georgy

doi:10.1016/j.anucene.2024.110532

Annals of Nuclear Energy

2024

DOI: 10.1016/j.anucene.2024.110532

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Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor

Ruziya Kelsingazina,

Vladimir Vityuk,

Alexander Vurim

et al.

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2024

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Study of Neutronic Processes Determining the Nature of Nuclear Heating of Materials in the Impulse Graphite Reactor

Kelsingazina,

Vityuk,

Vityuk

et al. 2024

jour

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Tightening the requirements for methodological support for in-pile experiments determines the need to improve the quality of predicting parameters of irradiated experimental devices that are important from a safety point of view. To qualitatively predict the temperature of device elements during irradiation in the IGR reactor, this paper presents an analysis of the radiation heating mechanisms under the influence of neutron and gamma fields of the reactor. Calculations were conducted to determine the contribution of various neutronic processes to the resulting nuclear heating of samples of structural materials during their planned irradiation in the IGR reactor, and the volumetric distribution of energy release in samples of structural materials was determined.

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Study of Neutronic Processes Determining the Nature of Nuclear Heating of Materials in the Impulse Graphite Reactor

Kelsingazina,

Vityuk,

Vityuk

et al. 2024

jour

View full text Add to dashboard Cite

show abstract

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Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor

Cited by 1 publication

References 17 publications

Study of Neutronic Processes Determining the Nature of Nuclear Heating of Materials in the Impulse Graphite Reactor

Study of Neutronic Processes Determining the Nature of Nuclear Heating of Materials in the Impulse Graphite Reactor

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