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Forrest B. Brown
Forrest B. Brown
LANL & University of New Mexico Nuclear Engineering
Verified email at q.com - Homepage
Title
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Cited by
Year
ENDF/B-VIII. 0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data
DA Brown, MB Chadwick, R Capote, AC Kahler, A Trkov, MW Herman, ...
Nuclear Data Sheets 148, 1-142, 2018
29502018
Initial MCNP6 release overview
T Goorley, M James, T Booth, F Brown, J Bull, LJ Cox, J Durkee, J Elson, ...
Nuclear technology 180 (3), 298-315, 2012
17672012
MCNP users manual-code version 6.2
CJ Werner, J Armstrong, FB Brown
Los Alamos national laboratory 108, 2017
10882017
Initial MCNP6 release overview-MCNP6 version 1.0
JT Goorley, MR James, TE Booth, FB Brown, JS Bull, LJ Cox, ...
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States), 2013
6162013
MCNP6. 2 release notes
CJ Werner, JS Bull, CJ Solomon, FB Brown, GW McKinney, ME Rising, ...
Los Alamos National Laboratory, report LA-UR-18-20808, 2018
4332018
MCNP version 6.2 release notes
CJ Werner, JS Bull, CJ Solomon, FB Brown, GW McKinney, ME Rising, ...
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States), 2018
3212018
MCNP® code version 6.3. 0 theory & user manual
JA Kulesza, TR Adams, JC Armstrong, SR Bolding, FB Brown, JS Bull, ...
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States), 2022
3182022
MCNP version 5
FB Brown, RF Barrett, TE Booth, JS Bull, LJ Cox, RA Forster, TJ Goorley, ...
Trans. Am. Nucl. Soc 87 (273), 02-3935, 2002
3172002
Features of MCNP6
T Goorley, M James, T Booth, F Brown, J Bull, LJ Cox, J Durkee, J Elson, ...
SNA+ MC 2013-joint international conference on supercomputing in nuclear …, 2014
2612014
Mcnp–a general monte carlo n-particle transport code, version 5
FB Brown
Los Alamos National Laboratory, Oak Ridge, TN, 2003
2372003
MCNP™ version 5
RA Forster, LJ Cox, RF Barrett, TE Booth, JF Briesmeister, FB Brown, ...
Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2004
2142004
MCNP–a general Monte Carlo N-particle transport code
FB Brown
Los Alamos, NM: Los Alamos National Laboratory, 2003
2142003
Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo
BC Kiedrowski, FB Brown, PPH Wilson
Nuclear Science and Engineering 168 (3), 226-241, 2011
2062011
On the use of Shannon entropy of the fission distribution for assessing convergence of Monte Carlo criticality calculations
FB Brown
ANS topical meeting on reactor physics (PHYSOR 2006). Canadian Nuclear …, 2006
1512006
Monte Carlo methods for radiation transport analysis on vector computers
FB Brown, WR Martin
Progress in Nuclear Energy 14 (3), 269-299, 1984
1511984
Fundamentals of Monte Carlo particle transport
FB Brown
Los Alamos National Laboratory, LA-UR-05-4983, 2005
1442005
Adjoint-Based k-Eigenvalue Sensitivity Coefficients to Nuclear Data Using Continuous-Energy Monte Carlo
BC Kiedrowski, FB Brown
Nuclear science and Engineering 174 (3), 227-244, 2013
1312013
MCNP5-1.60 release notes
F Brown, B Kiedrowski, J Bull
Los Alamos National Laboratory. Los Alamos, New Mexico: LA-UR-10-06235, 2010
1272010
Stochastic geometry capability in MCNP5 for the analysis of particle fuel
FB Brown, WR Martin
Annals of Nuclear Energy 31 (17), 2039-2047, 2004
1192004
Whisper: Sensitivity/uncertainty-based computational methods and software for determining baseline upper subcritical limits
BC Kiedrowski, FB Brown, JL Conlin, JA Favorite, AC Kahler, AR Kersting, ...
Nuclear Science and Engineering 181 (1), 17-47, 2015
1172015
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