William R Martin
William R Martin
Professor of Nuclear Engineering, University of Michigan
Verified email at umich.edu
Cited by
Cited by
Transport Theory
JJ Duderstadt, WR Martin
Wiley-Interscience, New York, 1979
Assessing risk factors for transmission of infection
JS Koopman, IM Longini Jr, JA Jacquez, CP Simon, DG Ostrow, ...
American Journal of Epidemiology 133 (12), 1199-1209, 1991
Diffusion synthetic acceleration of discontinuous finite element transport iterations
ML Adams, WR Martin
Nuclear science and engineering 111 (2), 145-167, 1992
Monte Carlo methods for radiation transport analysis on vector computers
FB Brown, WR Martin
Elsevier, 1984
Overview of development and design of MPACT: Michigan parallel characteristics transport code
B Kochunas, B Collins, D Jabaay, TJ Downar, WR Martin
Proceedings of the 2013 International Conference on Mathematics and …, 2013
Stochastic geometry capability in MCNP5 for the analysis of particle fuel
FB Brown, WR Martin
Annals of Nuclear Energy 31 (17), 2039-2047, 2004
On-the-fly Doppler broadening for Monte Carlo codes
G Yesilyurt, WR Martin, FB Brown
Nuclear science and engineering 171 (3), 239-257, 2012
Challenges and prospects for whole-core Monte Carlo analysis
WR Martin
Nuclear Engineering and Technology 44 (2), 151-160, 2012
Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report
C Oh
Idaho National Laboratory (INL), 2006
Finite element solutions of the neutron transport equation with applications to strong heterogeneities
WR Martin, JJ Duderstadt
Nuclear Science and Engineering 62 (3), 371-390, 1977
Monte Carlo performance benchmark for detailed power density calculation in a full size reactor core
JE Hoogenboom, WR Martin, B Petrovic
Benchmark specifications revision 1 (1), 2011
The Monte Carlo performance benchmark test-aims, specifications and first results
JE Hoogenboom, WR Martin, B Petrovic
International Conference on Mathematics and Computational Methods Applied to …, 2011
Status of vectorized Monte Carlo for particle transport analysis
WR Martin, FB Brown
The International Journal of Supercomputing Applications 1 (2), 11-32, 1987
Monte Carlo-advances and challenges
FB Brown, RD Mosteller, WR Martin
Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2008
Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR
JL Conlin, W Ji, JC Lee, WR Martin
Trans. Am. Nucl. Soc 92, 225-227, 2005
Phase-space finite element methods applied to the first-order form of the transport equation
WR Martin, CE Yehnert, L Lorence, JJ Duderstadt
Annals of Nuclear Energy 8 (11-12), 633-646, 1981
Theory and applications of the fission matrix method for continuous-energy Monte Carlo
S Carney, F Brown, B Kiedrowski, W Martin
Annals of Nuclear Energy 73, 423-431, 2014
Radiative effects in radiative shocks in shock tubes
High Energy Density Physics 7, 130-140, 2011
SCALE continuous-energy eigenvalue sensitivity coefficient calculations
CM Perfetti, BT Rearden, WR Martin
Nuclear Science and Engineering 182 (3), 332-353, 2016
Stochastic geometry and HTGR modeling with MCNP5
FB Brown, WR Martin, W Ji, JL Conlin, JC Lee
ANS Monte Carlo 2005 Topical Meeting, Chattanooga, TN, 2005
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