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    Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001::page 11005
    Author:
    Honda, Yuki
    ,
    Fujimoto, Nozomu
    ,
    Sawahata, Hiroaki
    ,
    Takada, Shoji
    ,
    Sawa, Kazuhiro
    DOI: 10.1115/1.4033813
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The high-temperature engineering test reactor (HTTR) is a block-type high-temperature gas-cooled reactor (HTGR). There are 32 control rods (16 pairs) in the HTTR. Six of the pairs of control rods are located in a core region and the remainder are located in a reflector region surrounding the core. Inserting all control rods simultaneously at the reactor scram in a full-power operation presents difficulty in maintaining the integrity of the metallic sleeve of the control rod because the core temperature of the HTTR is too high. Therefore, a two-step control rod insertion method is adopted for the reactor scram. The calculated control rod worth at the first step showed a larger underestimation than the measured value in the second step, although the calculated results of the excess reactivity tests showed good agreement with the measured result in the criticality tests of the HTTR. It is concluded that a cell model for the control rod guide block with the control rod in the reflector region is not suitable. In addition, in the core calculation, the macroscopic cross section of a homogenized region of the control rod guide block with the control rod is used. Therefore, it would be one of the reasons that the neutron flux distribution around the control rod in control rod guide block in the reflector region cannot be simulated accurately by the conventional cell model. In the conventional cell model, the control rod guide block is surrounded by the fuel blocks only, although the control rods in the reflector region are surrounded by both the fuel blocks and the reflector blocks. The difference of the neutron flux distribution causes the large difference of a homogenized macroscopic cross-section set of the control rod guide block with the control rod. Therefore, in this paper, the cell model is revised for the control rod guide block with the control rod in the reflector region to account for the actual configuration around the control rod guide block in the reflector region. The calculated control rod worth at the first step using the improved cell model shows better results than the previous one.
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      Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4235401
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorHonda, Yuki
    contributor authorFujimoto, Nozomu
    contributor authorSawahata, Hiroaki
    contributor authorTakada, Shoji
    contributor authorSawa, Kazuhiro
    date accessioned2017-11-25T07:18:46Z
    date available2017-11-25T07:18:46Z
    date copyright2016/20/12
    date issued2017
    identifier issn2332-8983
    identifier otherners_3_1_011005.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235401
    description abstractThe high-temperature engineering test reactor (HTTR) is a block-type high-temperature gas-cooled reactor (HTGR). There are 32 control rods (16 pairs) in the HTTR. Six of the pairs of control rods are located in a core region and the remainder are located in a reflector region surrounding the core. Inserting all control rods simultaneously at the reactor scram in a full-power operation presents difficulty in maintaining the integrity of the metallic sleeve of the control rod because the core temperature of the HTTR is too high. Therefore, a two-step control rod insertion method is adopted for the reactor scram. The calculated control rod worth at the first step showed a larger underestimation than the measured value in the second step, although the calculated results of the excess reactivity tests showed good agreement with the measured result in the criticality tests of the HTTR. It is concluded that a cell model for the control rod guide block with the control rod in the reflector region is not suitable. In addition, in the core calculation, the macroscopic cross section of a homogenized region of the control rod guide block with the control rod is used. Therefore, it would be one of the reasons that the neutron flux distribution around the control rod in control rod guide block in the reflector region cannot be simulated accurately by the conventional cell model. In the conventional cell model, the control rod guide block is surrounded by the fuel blocks only, although the control rods in the reflector region are surrounded by both the fuel blocks and the reflector blocks. The difference of the neutron flux distribution causes the large difference of a homogenized macroscopic cross-section set of the control rod guide block with the control rod. Therefore, in this paper, the cell model is revised for the control rod guide block with the control rod in the reflector region to account for the actual configuration around the control rod guide block in the reflector region. The calculated control rod worth at the first step using the improved cell model shows better results than the previous one.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleStudy on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
    typeJournal Paper
    journal volume3
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4033813
    journal fristpage11005
    journal lastpage011005-6
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001
    contenttypeFulltext
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