Elmer E Lewis

  • 881 Citations
1969 …2019
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Personal profile

Research Interests

Computational method of neutron transport, nuclear reactor physics, reliability and risk assessment.

Professor Lewis's research has included combining finite elements with other methods for the solution of the Boltzmann equation for neutron transport problems in six-dimensional space-angle-energy phase space. Applications are primarily to the simulation of neutron transport in nuclear reactor cores.

His current investigations are focused on neutron transport methods for treating the complex interactions between fuel-coolant lattice structures and more global effects in large power reactor cores. Under investigation are hybrid finite element and finite subelement formulations for treating spatial variables, tailored spherical harmonic expansions in angle, and preconditioned Krylov algorithms for the solution response matrix methods on parallel computers.

A second area of interest is reliability and risk assessment, focusing on how it relates to the engineering design process and particularly on the complex relationships between how technical experts and the public perceive the risks that accompany modern technology.

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  • 1 Similar Profiles
Neutrons Engineering & Materials Science
Fluxes Engineering & Materials Science
Geometry Engineering & Materials Science
Lagrange multipliers Engineering & Materials Science
Polynomials Engineering & Materials Science
Reactor cores Engineering & Materials Science
Markov processes Engineering & Materials Science
Pressurized water reactors Engineering & Materials Science

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Grants 2010 2012

Research Output 1969 2019

Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method

Wang, Y., Li, Y., Zhang, T., Lewis, E. E., Smith, M. A., Yang, W. S. & Wu, H., Jan 1 2019, (Accepted/In press) In : Nuclear Science and Engineering.

Research output: Contribution to journalArticle

Fluxes
Pressurized water reactors
Program processors

Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations

Wang, Y., Zhang, T., Lewis, E. E., Yang, W. S., Smith, M. A. & Wu, H., Nov 1 2019, In : Progress in Nuclear Energy. 117, 102991.

Research output: Contribution to journalArticle

Neutrons
matrix
Parallel algorithms
Reactor cores
Data transfer
1 Citation (Scopus)

Acceleration of within group iteration for pin-by-pin calculations

Zhang, T., Lewis, E. E., Smith, M. A., Yang, W. S., Wang, Y. & Wu, H., Feb 1 2018, In : Annals of Nuclear Energy. 112, p. 225-235 11 p.

Research output: Contribution to journalArticle

Reactor cores
Neutrons
Physics
Polynomials
Geometry

Generalized partitioned matrix acceleration of variational nodal method

Wang, Y., Zhang, T., Lewis, E. E., Yang, W. S., Smith, M. A. & Wu, H., Jan 1 2018, In : Transactions of the American Nuclear Society. 118, p. 907-910 4 p.

Research output: Contribution to journalConference article

Generalized partitioned matrix acceleration of variational nodal method

Wang, Y., Zhang, T., Lewis, E. E., Yang, W. S., Smith, M. A. & Wu, H., Jan 1 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 907-910 4 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

Research output: Chapter in Book/Report/Conference proceedingConference contribution