| Year |
Citation |
Score |
| 2019 |
Wang Y, Li Y, Zhang T, Lewis EE, Smith MA, Yang WS, Wu H. Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method Nuclear Science and Engineering. 193: 652-662. DOI: 10.1080/00295639.2018.1542883 |
0.446 |
|
| 2019 |
Wang Y, Zhang T, Lewis EE, Yang WS, Smith MA, Wu H. Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations Progress in Nuclear Energy. 117: 102991. DOI: 10.1016/J.Pnucene.2019.03.007 |
0.445 |
|
| 2018 |
Zhang T, Lewis EE, Smith MA, Yang WS, Wang Y, Wu H. Acceleration of within group iteration for pin-by-pin calculations Annals of Nuclear Energy. 112: 225-235. DOI: 10.1016/J.Anucene.2017.10.006 |
0.448 |
|
| 2017 |
Zhang T, Wang Y, Lewis EE, Smith MA, Yang WS, Wu H. A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors Nuclear Science and Engineering. 188: 160-174. DOI: 10.1080/00295639.2017.1350002 |
0.367 |
|
| 2017 |
Zhang T, Lewis EE, Smith MA, Yang WS, Wu H. A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors Nuclear Science and Engineering. 186: 120-133. DOI: 10.1080/00295639.2016.1273023 |
0.434 |
|
| 2015 |
Li Y, Lewis EE, Smith MA, Wu H, Cao L. Preconditioned multigroup GMRES algorithms for the variational nodal method Nuclear Science and Engineering. 179: 42-58. DOI: 10.13182/Nse13-103 |
0.324 |
|
| 2013 |
Lewis EE, Li Y, Smith MA, Yang WS, Wollaber AB. Preconditioned krylov solution of response matrix equations Nuclear Science and Engineering. 173: 222-232. DOI: 10.13182/Nse11-106 |
0.478 |
|
| 2010 |
Lewis EE. Second-order neutron transport methods Nuclear Computational Science: a Century in Review. 85-115. DOI: 10.1007/978-90-481-3411-3_2 |
0.438 |
|
| 2009 |
Lewis EE, Smith MA, Palmiotti G. A new paradigm for local-global coupling in whole-core neutron transport Nuclear Science and Engineering. 161: 279-288. DOI: 10.13182/Nse161-279 |
0.466 |
|
| 2008 |
Lewis EE, Smith MA, Palmiotti G. Three-dimensional neutron transport with novel local-global coupling International Conference On the Physics of Reactors 2008, Physor 08. 1: 589-594. |
0.38 |
|
| 2007 |
Lewis EE, Smith MA, Palmiotti G. A new paradigm for whole core neutron transport without homogenization Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007. |
0.362 |
|
| 2006 |
Zhang H, Lewis EE. Generalization of the variational nodal method to spherical harmonics approximations in R-Z geometry Nuclear Science and Engineering. 152: 29-36. DOI: 10.13182/Nse06-A2560 |
0.442 |
|
| 2006 |
Criekingen SV, Lewis EE, Beauwens R. Mixed-hybrid transport discretization using even and odd PN expansions Nuclear Science and Engineering. 152: 149-163. DOI: 10.13182/Nse06-1 |
0.593 |
|
| 2006 |
Smith MA, Lewis EE, Na BC. Benchmark on deterministic 3-D MOX fuel assembly transport calculations without spatial homogenization Progress in Nuclear Energy. 48: 383-393. DOI: 10.1016/J.Pnucene.2006.01.002 |
0.429 |
|
| 2006 |
Van Criekingen S, Beauwens R, Jerome JW, Lewis EE. Mixed-hybrid discretization methods for the linear Boltzmann transport equation Computer Methods in Applied Mechanics and Engineering. 195: 2719-2741. DOI: 10.1016/J.Cma.2005.06.002 |
0.738 |
|
| 2006 |
Smith MA, Lewis EE, Palmiotti G, Yang WS. A first-order integral method developed for the VARIANT code Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006. |
0.373 |
|
| 2006 |
Van Criekingen S, Lewis EE, Beauwens R. Mixed-hybrid transport discretization using even and odd P N Expansions Nuclear Science and Engineering. 152: 149-163. |
0.743 |
|
| 2006 |
Lewis EE, Smith MA, Palmiotti G. Quasi-reflected interface conditions for variational nodal lattice calculations Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006. |
0.366 |
|
| 2005 |
Yang WS, Smith MA, Palmiotti G, Lewis EE. Interface conditions for spherical harmonics methods Nuclear Science and Engineering. 150: 257-266. DOI: 10.13182/Nse05-1 |
0.471 |
|
| 2004 |
Smith MA, Palmiotti G, Lewis EE, Tsoulfanidis N. An integral form of the variational nodal method Nuclear Science and Engineering. 146: 141-151. DOI: 10.13182/Nse146-141 |
0.453 |
|
| 2004 |
Smith MA, Lewis EE, Na BC. Benchmark on deterministic 2-D MOX fuel assembly transport calculations without spatial homogenization Progress in Nuclear Energy. 45: 107-118. DOI: 10.1016/j.pnucene.2004.09.003 |
0.308 |
|
| 2004 |
Lewis EE. Much ado about nothing: Response matrices for void regions Annals of Nuclear Energy. 31: 2025-2037. DOI: 10.1016/J.Anucene.2004.07.008 |
0.503 |
|
| 2004 |
Smith MA, Lewis EE, Palmiotti G, Yang WS. A first-order spherical harmonics formulation compatible with the variational nodal method Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 1495-1503. |
0.401 |
|
| 2004 |
Van Criekingen S, Lewis EE, Beauwens R. Mixed-hybrid methods for the linear transport equation Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 1449-1458. |
0.733 |
|
| 2003 |
Smith MA, Tsoulfanidis N, Lewis EE, Palmiotti G, Taiwo TA. A finite subelement generalization of the variational nodal method Nuclear Science and Engineering. 144: 36-46. DOI: 10.1016/J.Pnueene.2004.09.001 |
0.477 |
|
| 2002 |
Zhang H, Lewis EE. Spatial adaptivity applied to the variational nodal Pn equations Nuclear Science and Engineering. 142: 57-63. DOI: 10.13182/Nse02-A2287 |
0.498 |
|
| 2002 |
Zhang H, Lewis EE. Spatial adaptivity applied to the variational nodal Pn equations Nuclear Science and Engineering. 142: 57-63. |
0.408 |
|
| 2001 |
Yang WS, Palmiotti G, Lewis EE. Numerical optimization of computing algorithms of the variational nodal method based on transformation of variables Nuclear Science and Engineering. 139: 174-185. DOI: 10.13182/Nse01-A2230 |
0.485 |
|
| 2001 |
Zhang H, Lewis EE. An Adaptive Approach to Variational Nodal Diffusion Problems Nuclear Science and Engineering. 137: 14-22. DOI: 10.13182/Nse01-A2172 |
0.444 |
|
| 2001 |
Zhang H, Lewis EE. Adaptive approach to variational nodal diffusion problems Nuclear Science and Engineering. 137: 14-22. |
0.344 |
|
| 1998 |
Lewis EE, Palmiotti G. Red-black response matrix acceleration by transformation of interface variables Nuclear Science and Engineering. 130: 181-193. DOI: 10.13182/Nse98-A1999 |
0.424 |
|
| 1997 |
Lewis EE, Palmiotti G. Simplified spherical harmonics in the variational nodal method Nuclear Science and Engineering. 126: 48-58. DOI: 10.13182/Nse97-A24456 |
0.477 |
|
| 1996 |
Laurin-Kovitz KF, Lewis EE. Variational nodal transport perturbation theory Nuclear Science and Engineering. 123: 369-380. DOI: 10.13182/Nse96-A24200 |
0.445 |
|
| 1996 |
Lewis EE, Carrico CB, Palmiotti G. Variational nodal formulation for the spherical harmonics equations Nuclear Science and Engineering. 122: 194-203. DOI: 10.13182/Nse96-1 |
0.404 |
|
| 1993 |
Palmiotti G, Carrico CB, Lewis EE. Variational nodal transport methods with anisotropic scattering Airport Pavement Innovations Theory to Practice. 233-243. DOI: 10.13182/Nse92-110 |
0.395 |
|
| 1992 |
Carrico CB, Lewis EE, Palmiotti G. Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations Nuclear Science and Engineering. 111: 168-179. DOI: 10.13182/Nse92-1 |
0.499 |
|
| 1991 |
Carrico CB, Lewis EE. Variational nodal transport solutions of multigroup criticality problems Progress in Nuclear Energy. 25: 99-106. DOI: 10.1016/0149-1970(91)90004-9 |
0.455 |
|
| 1990 |
Lewis EE, Hanebutte UR. A two-dimensional nonlinear response matrix method with scattering and absorption-emission Transport Theory and Statistical Physics. 19: 387-403. DOI: 10.1080/00411459008203897 |
0.392 |
|
| 1989 |
Lewis EE. Interface angular coupling reductions in variational nodal methods for neutron transport Nuclear Science and Engineering. 102: 140-152. DOI: 10.13182/Nse89-A23639 |
0.489 |
|
| 1986 |
Lewis EE, Dilber I. Finite element, nodal and response matrix methods: A variational synthesis for neutron transport Progress in Nuclear Energy. 18: 63-74. DOI: 10.1016/0149-1970(86)90013-2 |
0.508 |
|
| 1986 |
Lewis EE, Zhuguo T. Monte Carlo reliability modeling by inhomogeneous Markov processes Reliability Engineering. 16: 277-296. DOI: 10.1016/0143-8174(86)90098-3 |
0.318 |
|
| 1985 |
Dilber I, Lewis EE. VARIATIONAL NODAL METHODS FOR NEUTRON TRANSPORT Nuclear Science and Engineering. 91: 132-142. DOI: 10.13182/Nse85-A27436 |
0.46 |
|
| 1985 |
Zhuguo T, Lewis EE. Component dependency models in Markov Monte Carlo simulation Reliability Engineering. 13: 45-61. DOI: 10.1016/0143-8174(85)90057-5 |
0.304 |
|
| 1984 |
Lewis EE, Böhm F. Monte Carlo simulation of Markov unreliability models Nuclear Engineering and Design. 77: 49-62. DOI: 10.1016/0029-5493(84)90060-8 |
0.356 |
|
| 1984 |
Dilber I, Lewis EE. COMPARISON OF VARIATIONAL COARSE-MESH METHODS Transactions of the American Nuclear Society. 46: 401-402. |
0.445 |
|
| 1983 |
Thomas WA, Lewis EE. TWO VECTORIZED ALGORITHMS FOR THE SOLUTION OF THREE-DIMENSIONAL NEUTRON DIFFUSION EQUATIONS Nuclear Science and Engineering. 84: 67-71. DOI: 10.13182/Nse83-A17459 |
0.374 |
|
| 1981 |
Lewis EE, Ozgener HA. The constrained finite element approach to coarse-mesh transport computations Annals of Nuclear Energy. 8: 683-687. DOI: 10.1016/0306-4549(81)90135-3 |
0.476 |
|
| 1980 |
Blomquist RN, Lewis EE. A Rigorous Treatment of Transverse Buckling Effects in Two-Dimensional Neutron Transport Computations Nuclear Science and Engineering. 73: 125-139. DOI: 10.13182/Nse80-A18693 |
0.352 |
|
| 1980 |
Briggs LL, Lewis EE. TWO-DIMENSIONAL CONSTRAINED FINITE ELEMENT METHOD FOR NONUNIFORM LATTICE PROBLEMS Nuclear Science and Engineering. 75: 76-87. |
0.352 |
|
| 1977 |
Lewis EE. PROGRESS IN MULTIDIMENSIONAL NEUTRON TRANSPORT COMPUTATION Nuclear Science and Engineering. 64: 279-293. DOI: 10.13182/Nse77-A27370 |
0.48 |
|
| 1977 |
Briggs LL, Lewis EE. COMPARISON OF CONSTRAINED FINITE ELEMENTS AND RESPONSE MATRICES AS ONE-DIMENSIONAL TRANSPORT APPROXIMATIONS Nuclear Science and Engineering. 63: 225-235. DOI: 10.13182/Nse77-A27035 |
0.515 |
|
| 1976 |
Yuan YC, Lewis EE, Miller WF. ITERATIVE SOLUTION METHODS FOR TWO-DIMENSIONAL FINITE ELEMENT APPROXIMATIONS IN NEUTRON TRANSPORT . 85-100. |
0.413 |
|
| 1975 |
Lewis EE, Miller WF, Henry TP. TWO-DIMENSIONAL FINITE ELEMENT METHOD FOR INTEGRAL NEUTRON TRANSPORT CALCULATIONS Nuclear Science and Engineering. 58: 203-212. DOI: 10.13182/Nse75-A28223 |
0.514 |
|
| 1975 |
Briggs LL, Miller WF, Lewis EE. RAY-EFFECT MITIGATION IN DISCRETE ORDINATE-LIKE ANGULAR FINITE ELEMENT APPROXIMATIONS IN NEUTRON TRANSPORT Nuclear Science and Engineering. 57: 205-217. DOI: 10.13182/Nse75-A26752 |
0.5 |
|
| 1973 |
Miller WF, Lewis EE, Rossow EC. The Application of Phase-Space Finite Elements to the One-Dimensional Neutron Transport Equation Nuclear Science and Engineering. 51: 148-156. DOI: 10.13182/Nse73-A26590 |
0.425 |
|
| 1973 |
Miller WF, Lewis EE, Rossow EC. APPLICATION OF PHASE-SPACE FINITE ELEMENTS TO THE TWO-DIMENSIONAL NEUTRON TRANSPORT EQUATION IN X-Y GEOMETRY Nuclear Science and Engineering. 52: 12-22. |
0.366 |
|
| 1972 |
Semenza LA, Lewis EE, Rossow EC. The Application of the Finite Element Method to the Multigroup Neutron Diffusion Equation Nuclear Science and Engineering. 47: 302-310. DOI: 10.13182/Nse72-A22416 |
0.43 |
|
| 1972 |
Huang ST, Lewis EE. Asymptotic PN and double PN approximations Journal of Nuclear Energy. 26: 231-236. DOI: 10.1016/0022-3107(72)90070-6 |
0.422 |
|
| 1969 |
Lewis EE. A polynomial approximation for integral transport calculations Journal of Nuclear Energy. 23: 87-97. DOI: 10.1016/0022-3107(69)90038-0 |
0.491 |
|
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