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    Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 20905
    Author:
    Petkov, Gueorgui I.
    DOI: 10.1115/1.4039000
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.
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      Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4252596
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    contributor authorPetkov, Gueorgui I.
    date accessioned2019-02-28T11:05:37Z
    date available2019-02-28T11:05:37Z
    date copyright3/5/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_02_020905.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252596
    description abstractAnalysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEnhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
    typeJournal Paper
    journal volume4
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4039000
    journal fristpage20905
    journal lastpage020905-11
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
    contenttypeFulltext
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