Computing the Matrix Exponential in Burnup Calculations

Maria Pusa, Jaakko Leppänen

Research output: Contribution to journalArticleScientificpeer-review

101 Citations (Scopus)

Abstract

The topic of this paper is the computation of the matrix exponential in the context of burnup equations. The established matrix exponential methods are introduced briefly. The eigenvalues of the burnup matrix are important in choosing the matrix exponential method, and their characterization is considered. Based on the characteristics of the burnup matrix, the Chebyshev rational approximation method (CRAM) and its interpretation as a numeric contour integral are discussed in detail. The introduced matrix exponential methods are applied to two test cases representing an infinite pressurized water reactor pin-cell lattice, and the numerical results are presented. The results suggest that CRAM is capable of providing a robust and accurate solution to the burnup equations with a very short computation time.
Original languageEnglish
Pages (from-to)140-150
Number of pages11
JournalNuclear Science and Engineering
Volume164
Issue number2
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed

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abstract = "The topic of this paper is the computation of the matrix exponential in the context of burnup equations. The established matrix exponential methods are introduced briefly. The eigenvalues of the burnup matrix are important in choosing the matrix exponential method, and their characterization is considered. Based on the characteristics of the burnup matrix, the Chebyshev rational approximation method (CRAM) and its interpretation as a numeric contour integral are discussed in detail. The introduced matrix exponential methods are applied to two test cases representing an infinite pressurized water reactor pin-cell lattice, and the numerical results are presented. The results suggest that CRAM is capable of providing a robust and accurate solution to the burnup equations with a very short computation time.",
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Computing the Matrix Exponential in Burnup Calculations. / Pusa, Maria; Leppänen, Jaakko.

In: Nuclear Science and Engineering, Vol. 164, No. 2, 2010, p. 140-150.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Computing the Matrix Exponential in Burnup Calculations

AU - Pusa, Maria

AU - Leppänen, Jaakko

PY - 2010

Y1 - 2010

N2 - The topic of this paper is the computation of the matrix exponential in the context of burnup equations. The established matrix exponential methods are introduced briefly. The eigenvalues of the burnup matrix are important in choosing the matrix exponential method, and their characterization is considered. Based on the characteristics of the burnup matrix, the Chebyshev rational approximation method (CRAM) and its interpretation as a numeric contour integral are discussed in detail. The introduced matrix exponential methods are applied to two test cases representing an infinite pressurized water reactor pin-cell lattice, and the numerical results are presented. The results suggest that CRAM is capable of providing a robust and accurate solution to the burnup equations with a very short computation time.

AB - The topic of this paper is the computation of the matrix exponential in the context of burnup equations. The established matrix exponential methods are introduced briefly. The eigenvalues of the burnup matrix are important in choosing the matrix exponential method, and their characterization is considered. Based on the characteristics of the burnup matrix, the Chebyshev rational approximation method (CRAM) and its interpretation as a numeric contour integral are discussed in detail. The introduced matrix exponential methods are applied to two test cases representing an infinite pressurized water reactor pin-cell lattice, and the numerical results are presented. The results suggest that CRAM is capable of providing a robust and accurate solution to the burnup equations with a very short computation time.

U2 - 10.13182/NSE09-14

DO - 10.13182/NSE09-14

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JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

SN - 0029-5639

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