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dc.contributor.authorLi, Jian
dc.contributor.authorShe, Ding
dc.contributor.authorShi, Lei
dc.date.accessioned2019-02-28T11:05:32Z
dc.date.available2019-02-28T11:05:32Z
dc.date.copyright3/5/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_02_021007.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252584
dc.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.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleResearch on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4038771
dc.journal.fristpage21007
dc.journal.lastpage021007-4
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
dc.contenttypeFulltext


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