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    Numerical Study of High Temperature and High Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 004::page 41006
    Author:
    Akyuzlu, Kazim M.
    DOI: 10.1115/1.4030833
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Two mathematical models (a onedimensional (1D) and a twodimensional (2D)) were adopted to study, numerically, the thermalhydrodynamic characteristics of flow inside the cooling channels of a nuclear thermal rocket (NTR) engine. In the present study, only one of the cooling channels of the reactor core is simulated. The 1D model adopted here assumes the flow in this cooling channel to be unsteady, compressible, turbulent, and subsonic. The governing equations of the compressible flow in the cooling channel are discretized using a secondorder accurate (MacCormack) finitedifference scheme. The steadystate results of the proposed model were compared to the predictions by a commercial CFD code. The 2D CFD solution was obtained in two domains: the coolant (gaseous hydrogen) and the ZrC fuel cladding. The wall heat flux which varied along the channel length (as described by the nuclear variation in the nuclear power generation) was given as an input. Numerical experiments were carried out using both codes to simulate the thermal and hydrodynamic characteristics of the flow inside a singlecooling channel of the reactor for a typical Nuclear Engine for Rocket Vehicle Application (NERVA)type NTR engine. It is concluded that both models predict successfully the steadystate axial distributions of temperature, pressure, density, and velocity of gaseous hydrogen flow in the NTR cooling channel.
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      Numerical Study of High Temperature and High Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

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    https://yetl.yabesh.ir/yetl1/handle/yetl/159271
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    contributor authorAkyuzlu, Kazim M.
    date accessioned2017-05-09T01:22:13Z
    date available2017-05-09T01:22:13Z
    date issued2015
    identifier issn2332-8983
    identifier otherNERS_1_4_041006.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159271
    description abstractTwo mathematical models (a onedimensional (1D) and a twodimensional (2D)) were adopted to study, numerically, the thermalhydrodynamic characteristics of flow inside the cooling channels of a nuclear thermal rocket (NTR) engine. In the present study, only one of the cooling channels of the reactor core is simulated. The 1D model adopted here assumes the flow in this cooling channel to be unsteady, compressible, turbulent, and subsonic. The governing equations of the compressible flow in the cooling channel are discretized using a secondorder accurate (MacCormack) finitedifference scheme. The steadystate results of the proposed model were compared to the predictions by a commercial CFD code. The 2D CFD solution was obtained in two domains: the coolant (gaseous hydrogen) and the ZrC fuel cladding. The wall heat flux which varied along the channel length (as described by the nuclear variation in the nuclear power generation) was given as an input. Numerical experiments were carried out using both codes to simulate the thermal and hydrodynamic characteristics of the flow inside a singlecooling channel of the reactor for a typical Nuclear Engine for Rocket Vehicle Application (NERVA)type NTR engine. It is concluded that both models predict successfully the steadystate axial distributions of temperature, pressure, density, and velocity of gaseous hydrogen flow in the NTR cooling channel.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleNumerical Study of High Temperature and High Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core
    typeJournal Paper
    journal volume1
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4030833
    journal fristpage41006
    journal lastpage41006
    treeJournal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 004
    contenttypeFulltext
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