Zobrazeno 1 - 4
of 4
pro vyhledávání: '"Elizabeth Carol Selcow"'
Autor:
Jeremy Ed Sweezy, Konstantin K. Gudima, H. Grady Hughes, Jeffrey S. Bull, Stepan G. Mashnik, Lon-Chang Liu, Sergei Striganov, Arnold J. Sierk, Richard E. Prael, John D. Zumbro, Robert C. Little, Elizabeth Carol Selcow, Forrest B. Brown, Nikolai Mokhov, John T. Goorley
Publikováno v:
Radiation Protection Dosimetry. 116:109-112
The developmental version of MCNP5 has recently been extended to provide for continuous-energy transport of high-energy protons. This enhancement involves the incorporation of several significant new physics models into the code. Multiple Coulomb sca
Autor:
H. G. Hughes, Elizabeth Carol Selcow, J. D. Zumbro, Richard E. Prael, Jeffrey S. Bull, A. Acuff
Publikováno v:
Radiation Protection Dosimetry. 117:447-452
A modified version of MCNP5 has been developed to treat continuous-energy proton transport. This work is summarised in companion papers by Hughes et al. and Bull et al. (in these proceedings). An intrinsic part of this development effort has involved
Autor:
Richard E. Prael, Forrest B. Brown, Elizabeth Carol Selcow, Avneet Sood, Gregg C Geisler, Judith F. Briesmeister, R. Arthur Forster, Susan E Post, John T. Goorley, Richard Barrett, L. J. Cox, Jeffrey S. Bull, Russell D. Mosteller, Thomas E. Booth
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 213:82-86
The Monte Carlo transport workhorse, MCNP [Los Alamos National Laboratory report LA-13709-M, 2000], is undergoing a massive renovation at Los Alamos National Laboratory (LANL) in support of the Eolus Project of the Advanced Simulation and Computing (
Autor:
Elizabeth Carol Selcow, Thomas E. Booth, John S. Hendricks, L. J. Cox, S. W. White, Gregg W. McKinney, R. A. Forster, Avneet Sood, Russell D. Mosteller, Judith F. Briesmeister, Richard E. Prael
Publikováno v:
Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications ISBN: 9783642621130
The Los Alamos National Laboratory Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron-gamma radiation transport applications. These include nuclear criticality safety, radiation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88e693f737bbd8a8cc210fa879a8962c
https://doi.org/10.1007/978-3-642-18211-2_103
https://doi.org/10.1007/978-3-642-18211-2_103