Zobrazeno 1 - 8
of 8
pro vyhledávání: '"R N Blomquist"'
Autor:
R. N. Blomquist, Ely M. Gelbard
Publikováno v:
Nuclear Science and Engineering. 141:85-100
We compare nominal efficiencies, i.e., variances in power shapes for equal running time, of different versions of the Monte Carlo (MC) eigenvalue computation. The two main methods considered here are 'conventional' MC and the superhistory method. Wit
Autor:
E. M. Gelbard, K. C. Gross, P. L. Garner, A. M. Tentner, R. N. Blomquist, T. R. Canfield, R. A. Valentin, M. Minkoff
Publikováno v:
Communications of the ACM. 37:54-64
Autor:
P N Brown, S McKinley, R N Blomquist, C J Dean, J C Sublet, R. E. MacFarlane, Y Lee, E F Plechaty, E Lent, D E Cullen, M E Dunn
In this report we consider three fast critical assemblies, each assembly is dominated by a different nuclear fuel: Godiva (U235), Jezebel (Pu239) and Jezebel23 (U233) [1]. We first show the improvement in results when using the new ENDF/B-VII.0 data
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a3ffd5200528932fd2434baaf150f89
https://doi.org/10.2172/921339
https://doi.org/10.2172/921339
Autor:
M Greene, E Lent, D E Cullen, J C Sublet, R. E. MacFarlane, S McKinley, R N Blomquist, E F Plechaty
We have compared the results produced by a variety of currently available Monte Carlo neutron transport codes for the relatively simple problem of a fast source of neutrons slowing down and thermalizing in water. Initial comparisons showed rather lar
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::82edef4259c76a070da7bc1eb121dcac
https://doi.org/10.2172/889442
https://doi.org/10.2172/889442
Autor:
D Cullen, R N Blomquist, C Dean, Y Lee, M Lee, M A Kalugin, D Heinrichs, A Trkov, R MacFarlan, Y Nagaya
I would like to determine how accurately a variety of neutron transport code packages (code and cross section libraries) can calculate simple integral parameters, such as K{sub eff}, for systems that are sensitive to thermal neutron scattering. Since
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08043710800a765335ad9ddae70efc14
https://doi.org/10.2172/15009834
https://doi.org/10.2172/15009834
Autor:
R. N. Blomquist, Ely M. Gelbard
We compare nominal efficiencies, i.e. variances in power shapes for equal running time, of different versions of the Monte Carlo eigenvalue computation, as applied to criticality safety analysis calculations. The two main methods considered here are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6a1b4ba2bf03c71a956641d85a9b0dc3
https://doi.org/10.2172/793906
https://doi.org/10.2172/793906
The COMMIX-LAR/P computer program is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-lA to include multiple
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b8bc3267137099a69365a4fb4a8be524
https://doi.org/10.2172/10117776
https://doi.org/10.2172/10117776
Autor:
B.S. Brown, A E Knox, D R Henley, R J Armani, A. W. Schulke, A G Hins, J L Bailey, J.M. Carpenter, B A Loomis, R N Blomquist
We describe the Enriched Uranium Booster Target designed for use in Argonne's Intense Pulsed Neutron Source. This report contains a general description of the system, and descriptions of the thermal-hydraulic and loss-of-coolant accident analyses, of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::07956aef992acd293dbe99e4655e785b
https://doi.org/10.2172/6944951
https://doi.org/10.2172/6944951