TY - JOUR
T1 - Uncertainty quantification for multigroup diffusion equations using sparse tensor approximations
AU - Fuenzalida, Consuelo
AU - Jerez-Hanckes, Carlos
AU - McClarren, Ryan G.
N1 - Funding Information:
∗Submitted to the journal’s Computational Methods in Science and Engineering section May 7, 2018; accepted for publication (in revised form) April 3, 2019; published electronically June 20, 2019. http://www.siam.org/journals/sisc/41-3/M118599.html Funding: This work was partially supported by the Corfo 2030 Seed Fund Program TAMU-PUC 201603 and Fondecyt Regular 1171491. †School of Engineering, Pontificia Universidad Católica de Chile, Santiago, Chile (mcfuenzalida@ uc.cl). ‡Faculty of Engineering and Sciences, Universidad Adolfo Ibañez, Santiago, Chile (carlos.jerez@uai.cl). §Department of Aerospace and Mechanical Engineering, College of Engineering, University of Notre Dame, Notre Dame, IN 46556 (rmcclarr@nd.edu).
Publisher Copyright:
© 2019 Society for Industrial and Applied Mathematics
PY - 2019
Y1 - 2019
N2 - We develop a novel method to compute first and second order statistical moments of the neutron kinetic density inside a nuclear system by solving the energy-dependent neutron diffusion equation. Randomness comes from the lack of precise knowledge of external sources as well as of the interaction parameters, known as cross sections. Thus, the density is itself a random variable. As Monte Carlo simulations entail intense computational work, we are interested in deterministic approaches to quantify uncertainties. By assuming as given the first and second statistical moments of the excitation terms, a sparse tensor finite element approximation of the first two statistical moments of the dependent variables for each energy group can be efficiently computed in one run. Numerical experiments provided validate our derived convergence rates and point to further research avenues.
AB - We develop a novel method to compute first and second order statistical moments of the neutron kinetic density inside a nuclear system by solving the energy-dependent neutron diffusion equation. Randomness comes from the lack of precise knowledge of external sources as well as of the interaction parameters, known as cross sections. Thus, the density is itself a random variable. As Monte Carlo simulations entail intense computational work, we are interested in deterministic approaches to quantify uncertainties. By assuming as given the first and second statistical moments of the excitation terms, a sparse tensor finite element approximation of the first two statistical moments of the dependent variables for each energy group can be efficiently computed in one run. Numerical experiments provided validate our derived convergence rates and point to further research avenues.
KW - Finite element method
KW - Multigroup diffusion equation
KW - Sparse tensor approximation
KW - Uncertainty quantification
UR - http://www.scopus.com/inward/record.url?scp=85071837570&partnerID=8YFLogxK
U2 - 10.1137/18M1185995
DO - 10.1137/18M1185995
M3 - Article
AN - SCOPUS:85071837570
SN - 1064-8275
VL - 41
SP - B545-B575
JO - SIAM Journal on Scientific Computing
JF - SIAM Journal on Scientific Computing
IS - 3
ER -