Transient Analysis of Conjugate Natural Convection in the Hottest Channel of MTR Nuclear Fuel Type

A numerical solution of the transient natural convection in the hottest channel of MTR nuclear fuel type is performed in this study by mean of the lumped parameter approach. After employing this approach, the momentum and the energy equations are reduced, to form a lumped parameter model. This model is solved numerically by the Runge-kutta method for a given reactor power according to an iterative process based on the balance between the buoyancy and the friction forces. After these forces are balanced the transient variation of the fuel, coolant and the reactor pool temperatures are carried out and used to evaluate the fuel and the coolant temperatures variation along the channel active length. Finally, the lumped parameter model (LPM) results are validated after we have obtained a good agreement with elsewhere published results of the Relap 5 code system.

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Publication Details

Journal
International Journal of Thermofluid Science and Technology
Published
2024-12-01
DOI
https://doi.org/10.36963/ijtst.110302
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Transient Analysis of Conjugate Natural Convection in the Hottest Channel of MTR Nuclear Fuel Type

Hamed Djalal
International Journal of Thermofluid Science and Technology
Nuclear Materials and Properties
article

Transient Analysis of Conjugate Natural Convection in the Hottest Channel of MTR Nuclear Fuel Type

Hamed Djalal
article en

Abstract

A numerical solution of the transient natural convection in the hottest channel of MTR nuclear fuel type is performed in this study by mean of the lumped parameter approach. After employing this approach, the momentum and the energy equations are reduced, to form a lumped parameter model. This model is solved numerically by the Runge-kutta method for a given reactor power according to an iterative process based on the balance between the buoyancy and the friction forces. After these forces are balanced the transient variation of the fuel, coolant and the reactor pool temperatures are carried out and used to evaluate the fuel and the coolant temperatures variation along the channel active length. Finally, the lumped parameter model (LPM) results are validated after we have obtained a good agreement with elsewhere published results of the Relap 5 code system.

International Journal of Thermofluid Science and TechnologyVol. 11(3)
Openalex Percentile: Top 84%
Nuclear Materials and Properties
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Transient Analysis of Conjugate Natural Convection in the Hottest Channel of MTR Nuclear Fuel Type — Hamed Djalal · International Journal of Thermofluid Science and Technology (2024) | TGRS Research Map | TGRS