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    Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003::page 31013
    Author:
    Honda, Yuki
    ,
    Sato, Hiroyuki
    ,
    Nakagawa, Shigeaki
    ,
    Ohashi, Hirofumi
    DOI: 10.1115/1.4039066
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: One of the key elements in probabilistic risk assessment is the identification and characterization of uncertainties. This paper suggests a procedure to identify influencing factors for uncertainty in source term evaluation, which are important to risk of public dose. We propose the following six steps for the identification in a systematic manner in terms of completeness and transparency of the results using both a logic diagram based on basic equations and expert opinions: (1) identification of uncertainty factors based on engineering knowledge of accident scenario analysis; (2) derivation of factors at the level of physical phenomena and variable parameters by expansion of dynamic equation for the system and scenario to be investigated, (3) extraction of uncertainties in variable parameters; (4) selection of important factors based on sensitivity study results and engineering knowledge; (5) identification of important factors for uncertainty analysis using expert opinions; and (6) integration of selected factors in the aforementioned steps. The proposed approach is tested with a case study for a risk-dominant accident scenario in direct cycle high-temperature gas-cooled reactor (HTGR) plant. We use this approach for evaluating the fuel temperature in terms of reactor dynamics and thermal hydraulic characteristics during a depressurized loss-of-forced circulation (DLOFC) accident with the failure of mitigation systems such as control rod systems (CRS) in a representative HTGR plan. In total, six important factors and 16 influencing factors were successfully identified by the proposed method in the case study. The selected influencing factors can be used as input parameters in uncertainty propagation analysis.
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      Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4252570
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorHonda, Yuki
    contributor authorSato, Hiroyuki
    contributor authorNakagawa, Shigeaki
    contributor authorOhashi, Hirofumi
    date accessioned2019-02-28T11:05:27Z
    date available2019-02-28T11:05:27Z
    date copyright5/16/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_03_031013.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252570
    description abstractOne of the key elements in probabilistic risk assessment is the identification and characterization of uncertainties. This paper suggests a procedure to identify influencing factors for uncertainty in source term evaluation, which are important to risk of public dose. We propose the following six steps for the identification in a systematic manner in terms of completeness and transparency of the results using both a logic diagram based on basic equations and expert opinions: (1) identification of uncertainty factors based on engineering knowledge of accident scenario analysis; (2) derivation of factors at the level of physical phenomena and variable parameters by expansion of dynamic equation for the system and scenario to be investigated, (3) extraction of uncertainties in variable parameters; (4) selection of important factors based on sensitivity study results and engineering knowledge; (5) identification of important factors for uncertainty analysis using expert opinions; and (6) integration of selected factors in the aforementioned steps. The proposed approach is tested with a case study for a risk-dominant accident scenario in direct cycle high-temperature gas-cooled reactor (HTGR) plant. We use this approach for evaluating the fuel temperature in terms of reactor dynamics and thermal hydraulic characteristics during a depressurized loss-of-forced circulation (DLOFC) accident with the failure of mitigation systems such as control rod systems (CRS) in a representative HTGR plan. In total, six important factors and 16 influencing factors were successfully identified by the proposed method in the case study. The selected influencing factors can be used as input parameters in uncertainty propagation analysis.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
    typeJournal Paper
    journal volume4
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4039066
    journal fristpage31013
    journal lastpage031013-11
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
    contenttypeFulltext
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