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    Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003::page 31301-1
    Author:
    Dwijayanto, R. Andika Putra
    ,
    Ardiansyah, Harun
    ,
    Harto, Andang Widi
    DOI: 10.1115/1.4064465
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Thermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using Monte Carlo N-particle 6.2 (MCNP6.2) and Serpent-2 reactor physics codes with evaluated nuclear data files/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. While the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.
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      Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4303600
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorDwijayanto, R. Andika Putra
    contributor authorArdiansyah, Harun
    contributor authorHarto, Andang Widi
    date accessioned2024-12-24T19:15:34Z
    date available2024-12-24T19:15:34Z
    date copyright4/17/2024 12:00:00 AM
    date issued2024
    identifier issn2332-8983
    identifier otherners_010_03_031301.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303600
    description abstractThermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using Monte Carlo N-particle 6.2 (MCNP6.2) and Serpent-2 reactor physics codes with evaluated nuclear data files/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. While the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleVerification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
    typeJournal Paper
    journal volume10
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4064465
    journal fristpage31301-1
    journal lastpage31301-7
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003
    contenttypeFulltext
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