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    Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 21007
    Author:
    Li, Jian
    ,
    She, Ding
    ,
    Shi, Lei
    DOI: 10.1115/1.4038771
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In depletion and transmutation calculation, it is important to solve detailed burnup chains with high computational accuracy and efficiency. This requires the good performance of the burnup algorithms. Nuclide inventory tool (NUIT) is a newly developed nuclide inventory calculation code, which is capable of handling detailed depletion chains by implementing various advanced algorithms. Based on the NUIT code, this paper investigates the accuracy and efficiency of the mini-max polynomial approximation (MMPA) method, and compares it with other burnup solvers in NUIT code. It is concluded that the MMPA method is numerically accurate and efficient for dealing with detailed depletion chains with extremely short half-lived nuclides.
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      Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4252584
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorLi, Jian
    contributor authorShe, Ding
    contributor authorShi, Lei
    date accessioned2019-02-28T11:05:32Z
    date available2019-02-28T11:05:32Z
    date copyright3/5/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_02_021007.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252584
    description abstractIn depletion and transmutation calculation, it is important to solve detailed burnup chains with high computational accuracy and efficiency. This requires the good performance of the burnup algorithms. Nuclide inventory tool (NUIT) is a newly developed nuclide inventory calculation code, which is capable of handling detailed depletion chains by implementing various advanced algorithms. Based on the NUIT code, this paper investigates the accuracy and efficiency of the mini-max polynomial approximation (MMPA) method, and compares it with other burnup solvers in NUIT code. It is concluded that the MMPA method is numerically accurate and efficient for dealing with detailed depletion chains with extremely short half-lived nuclides.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleResearch on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
    typeJournal Paper
    journal volume4
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4038771
    journal fristpage21007
    journal lastpage021007-4
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;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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