Edward W. Larsen
Affiliations: | Nuclear Engineering and Radiological Sciences | University of Michigan, Ann Arbor, Ann Arbor, MI |
Area:
Nuclear Engineering, StatisticsWebsite:
https://ners.engin.umich.edu/people/larsen-edward/Google:
"Edward Larsen"Parents
Sign in to add mentorGeorge Joseph Habetler | grad student | 1971 | RPI (Physics Tree) | |
(Completeness Results for Linear Operators in a Hilbert Space and Problems in Neutron Transport Theory) |
Children
Sign in to add traineeJeffery D. Densmore | grad student | 2002 | University of Michigan |
Kristy K. Brock-Leatherman | grad student | 2003 | University of Michigan |
Heath L. Hanshaw | grad student | 2005 | University of Michigan |
Martha M. Matuszak | grad student | 2007 | University of Michigan |
Philip M. Tchou | grad student | 2007 | University of Michigan |
Allan B. Wollaber | grad student | 2008 | University of Michigan |
Troy L. Becker | grad student | 2009 | University of Michigan |
Gregory G. Davidson | grad student | 2010 | University of Michigan |
Emily R. Wolters | grad student | 2011 | University of Michigan |
Jinan Yang | grad student | 2011 | University of Michigan |
Shikha Prasad | grad student | 2012 | University of Michigan |
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Publications
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Jarrett M, Kochunas B, Larsen E, et al. (2019) Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method Nuclear Science and Engineering. 193: 1291-1309 |
Yee BC, Kochunas B, Larsen EW. (2019) A Multilevel in Space and Energy Solver for 3-D Multigroup Diffusion and Coarse-Mesh Finite Difference Eigenvalue Problems Nuclear Science and Engineering. 193: 722-745 |
Jarrett M, Kochunas B, Larsen E, et al. (2018) Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization Nuclear Science and Engineering. 192: 219-239 |
Trahan TJ, Larsen EW. (2017) Variationally Derived Discontinuity Factors for the Asymptotic Homogenized Diffusion Equation Nuclear Science and Engineering. 185: 1-35 |
Yee BC, Kochunas B, Larsen EW, et al. (2017) Space-Dependent Wielandt Shifts for Multigroup Diffusion Eigenvalue Problems Nuclear Science and Engineering. 188: 140-159 |
Zhu A, Kochunas B, Xu Y, et al. (2017) Theoretical Convergence Rate Lower Bounds for Variants of Coarse Mesh Finite Difference to Accelerate Neutron Transport Calculations Nuclear Science and Engineering. 186: 224-238 |
Yee BC, Kochunas B, Larsen EW. (2017) A multilevel in space and energy solver for multigroup diffusion eigenvalue problems Nuclear Engineering and Technology. 49: 1125-1134 |
Kochunas B, Fitzgerald A, Larsen E. (2017) Fourier analysis of iteration schemes for k-eigenvalue transport problems with flux-dependent cross sections Journal of Computational Physics. 345: 294-307 |
Collins B, Stimpson S, Kelley BW, et al. (2016) Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT Journal of Computational Physics. 326: 612-628 |
Keady KP, Larsen EW. (2016) Stability of Monte Carlo k-eigenvalue simulations with CMFD feedback Journal of Computational Physics. 321: 947-964 |