Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Russell D. Mosteller"'
Autor:
Russell D. Mosteller
Publikováno v:
Nuclear Data Sheets. 118:442-445
Results obtained with the MCNP5 Monte Carlo code and the ENDF/B-VII.1 and ENDF/B-VII.0 nuclear data libraries have been compared for the 119 benchmarks in the expanded criticality validation suite for MCNP and for 23 additional benchmarks. ENDF/B-VII
Autor:
Russell D. Mosteller, Michael E Dunn, R.D. McKnight, A.C. Kahler, R M Lell, S.C. Frankle, R. E. MacFarlane, Said F. Mughabghab, T.H. Trumbull, Andrej Trkov, M.W. Herman, R. Arcilla, Giuseppe Palmiotti, H. Hiruta, Jean-Christophe Sublet, Brian C. Kiedrowski, Mark B. Chadwick
Publikováno v:
Nuclear Data Sheets. 112:2997-3036
The ENDF/B-VII.1 library is the latest revision to the United Statesʼ Evaluated Nuclear Data File (ENDF). The ENDF library is currently in its seventh generation, with ENDF/B-VII.0 being released in 2006. This revision expands upon that library, inc
Autor:
Toshihiko Kawano, Michael E Dunn, Phillip G. Young, T.H. Trumbull, S. C. van der Marck, David P. Heinrichs, M.L. Zerkle, R. Arcilla, Alejandro Sonzogni, David Brown, A. Courcelle, Gerald M. Hale, A.C. Kahler, David Livingstone Smith, H.C. Huria, Herve Derrien, V.G. Pronyaev, D. P. McNabb, S.C. Frankle, R. E. MacFarlane, William B. Wilson, Luiz C Leal, E.T. Cheng, C.L. Dunford, R.D. McKnight, Morgan C. White, J.P. Weinman, D. G. Madland, Nancy M. Larson, M.W. Herman, Peter Möller, Mark B. Chadwick, J.B. Briggs, K.S. Kozier, D. Rochman, Said F. Mughabghab, Russell D. Mosteller, P. Obložinský, N.M. Greene, Patrick Talou, R.C. Block, Holly R. Trellue, Allan D. Carlson, Philip R. Page, Boris Pritychenko, C.R. Lubitz, D.E. Cullen, R. C. Little
Publikováno v:
Nuclear Data Sheets. 107:2931-3060
We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group
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 (
Publikováno v:
Nuclear Science and Engineering. 145:105-119
The Zeus experiments have been designed to test the adequacy of {sup 235}U cross sections in the intermediate-energy range. Detailed models of the three Zeus critical experiments are developed for the MCNP Monte Carlo code, and calculated results, ba
Autor:
Frank J. Rahn, Russell D. Mosteller
Publikováno v:
Nuclear Technology. 110:168-180
The possibility of recriticality during the reflood phase of a severe accident in a boiling water reactor (BWR) is investigated. In addition, the fraction of control-rod material that must be retai...
Publikováno v:
Nuclear Science and Engineering. 107:265-271
The Doppler coefficient of reactivity is a crucial parameter in the evaluation of several transients in light water reactors (LWRs). It is relatively small in magnitude and cannot be measured direc...
Autor:
Russell D. Mosteller
Publikováno v:
AIP Conference Proceedings.
The MCNP Criticality Validation Suite is a collection of 31 benchmarks taken from the International Handbook of Evaluated Criticality Safety Benchmark Experiments. MCNP5 calculations clearly demonstrate that, overall, nuclear data for a preliminary v
Publikováno v:
Advances in Nuclear Science and Technology ISBN: 9780306455155
The United States evaluated nuclear database, ENDF/B, is organized and implemented by the Cross Section Evaluation Working Group (CSEWG), which is a cooperative industrial/governmental activity involving, at its peak, some 20 different organizations.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2fd0a5791c0874a58e350d1de13a3cd5
https://doi.org/10.1007/0-306-47811-0_4
https://doi.org/10.1007/0-306-47811-0_4
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