Show simple item record

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


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record