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    Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 002::page 21303-1
    Author:
    Ma, Yugao
    ,
    Liu, Minyun
    ,
    Xie, Biheng
    ,
    Han, Wenbin
    ,
    Chai, Xiaoming
    ,
    Huang, Shanfang
    ,
    Yu, Hongxing
    DOI: 10.1115/1.4051612
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Space fission power systems can enable ambitious solar-system and deep-space science missions. The heat pipe-cooled reactor is one of the most potential candidates for near-term space power supply, featuring safety, simplicity, reliability, and modularity. Heat pipe-cooled reactors are solid-state and high-temperature (up to 1500 K) reactors, where the thermal expansion is remarkable and the mechanical response significantly influences the neutronics and thermal analyses. Due to the considerable difference between heat pipe-cooled reactors and traditional water reactors in the structure and design concept, the coupling solutions for light water reactors cannot be directly applied to heat pipe-cooled reactor analyses. Therefore, a new coupling framework and program need to consider the coupling effects among neutronics, heat transfer, and mechanics. Based on the Monte Carlo program rmc and commercial finite element program ansysmechanicalansys parametric design language (APDL), this work introduces the three coupling fields of neutronics (N), thermal (T), and mechanics (M) for heat pipe cooled reactors. Besides, the finite element method and the Monte Carlo program use different meshes and geometry construction methods. Therefore, the spatial mapping and geometry reconstruction are also essential for the N/T-M coupling, which is discussed and established in detail. Furthermore, the N/T-M coupling methods are applied to the preliminary self-designed 10 kWel space heat pipe cooled reactor. Coupling shows that the thermal-mechanical feedback in the solid-state reactor has negative reactivity feedback (about −2000 pcm) while it has a deterioration in heat transfer due to the expansion in the gas gap.
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      Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4284023
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorMa, Yugao
    contributor authorLiu, Minyun
    contributor authorXie, Biheng
    contributor authorHan, Wenbin
    contributor authorChai, Xiaoming
    contributor authorHuang, Shanfang
    contributor authorYu, Hongxing
    date accessioned2022-05-08T08:30:57Z
    date available2022-05-08T08:30:57Z
    date copyright10/19/2021 12:00:00 AM
    date issued2021
    identifier issn2332-8983
    identifier otherners_008_02_021303.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284023
    description abstractSpace fission power systems can enable ambitious solar-system and deep-space science missions. The heat pipe-cooled reactor is one of the most potential candidates for near-term space power supply, featuring safety, simplicity, reliability, and modularity. Heat pipe-cooled reactors are solid-state and high-temperature (up to 1500 K) reactors, where the thermal expansion is remarkable and the mechanical response significantly influences the neutronics and thermal analyses. Due to the considerable difference between heat pipe-cooled reactors and traditional water reactors in the structure and design concept, the coupling solutions for light water reactors cannot be directly applied to heat pipe-cooled reactor analyses. Therefore, a new coupling framework and program need to consider the coupling effects among neutronics, heat transfer, and mechanics. Based on the Monte Carlo program rmc and commercial finite element program ansysmechanicalansys parametric design language (APDL), this work introduces the three coupling fields of neutronics (N), thermal (T), and mechanics (M) for heat pipe cooled reactors. Besides, the finite element method and the Monte Carlo program use different meshes and geometry construction methods. Therefore, the spatial mapping and geometry reconstruction are also essential for the N/T-M coupling, which is discussed and established in detail. Furthermore, the N/T-M coupling methods are applied to the preliminary self-designed 10 kWel space heat pipe cooled reactor. Coupling shows that the thermal-mechanical feedback in the solid-state reactor has negative reactivity feedback (about −2000 pcm) while it has a deterioration in heat transfer due to the expansion in the gas gap.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleNeutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
    typeJournal Paper
    journal volume8
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4051612
    journal fristpage21303-1
    journal lastpage21303-11
    page11
    treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 002
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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