Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Michael L Fensin"'
Publikováno v:
Annals of Nuclear Energy. 96:36-60
This burnup study examined the effect of a predicted critical control rod position on the nuclide predictability of several axial and radial locations within a 4 × 4 graphite moderated gas cooled reactor fuel cluster geometry. To achieve this, a con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4ca2b8ed8aa0b46f940061d4a51bc09a
https://doi.org/10.1016/j.anucene.2016.05.025
https://doi.org/10.1016/j.anucene.2016.05.025
Autor:
Michael L Fensin, Michael R. James
Publikováno v:
Annals of Nuclear Energy. 94:618-625
Though MCNP6 will transport elementary charged particles and light ions to low energies (i.e. less than 20 MeV), MCNP6 has historically relied on model physics with suggested minimum energies of ∼20 to 200 MeV. Use of library data for the low energ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::028a7b710023820fbd9ed18b006bd241
https://doi.org/10.1016/j.anucene.2016.03.025
https://doi.org/10.1016/j.anucene.2016.03.025
Publikováno v:
Nuclear Technology. 192:250-258
The mission of the Domestic Nuclear Detection Office is to quickly and reliably detect unauthorized attempts to import or transport special nuclear material for use against the United States. Devel...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a0d26c208090c6659122ef95faf3539
https://doi.org/10.13182/nt14-127
https://doi.org/10.13182/nt14-127
Autor:
Michael L Fensin, Marissa Umbel
Publikováno v:
Progress in Nuclear Energy. 85:719-728
Most of the development of the MCNPX/6 burnup capability focused on features that were applied to the Boltzman transport or used to prepare coefficients for use in CINDER90, with little change to CINDER90 or the CINDER90 data. Though a scheme exists
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4bdc4088d9a52ca7b1b7003a2f16bf14
https://doi.org/10.1016/j.pnucene.2015.09.001
https://doi.org/10.1016/j.pnucene.2015.09.001
Publikováno v:
Progress in Nuclear Energy. 83:186-190
The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. With the merger of MCNPX and MCNP5, MCNP6 combined the capability of both simulation t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8299bb9cf5e6f21ddab759c79be8e09c
https://doi.org/10.1016/j.pnucene.2015.03.017
https://doi.org/10.1016/j.pnucene.2015.03.017
Publikováno v:
Annals of Nuclear Energy. 81:150-163
A novel object-oriented modular mapping methodology for externally coupled neutronics–thermal hydraulics multiphysics simulations was developed. The Simulator using MCNP with Integrated Thermal-Hydraulics for Exploratory Reactor Studies (SMITHERS)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5413054d2edd9ea878f49dc0b76ee7e7
https://doi.org/10.1016/j.anucene.2015.03.027
https://doi.org/10.1016/j.anucene.2015.03.027
Publikováno v:
Progress in Nuclear Energy. 80:45-73
In March of 2009 the Next Generation Safeguards Initiative of the U.S. Department of Energy began a nominal five year spent fuel research effort with the goal of: (1) quantifying plutonium content in spent nuclear fuel through the use of non-destruct
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::488d5352e27d20ec332c5ec8df061425
https://doi.org/10.1016/j.pnucene.2014.10.012
https://doi.org/10.1016/j.pnucene.2014.10.012
Autor:
Jay S. Elson, Brian C. Kiedrowski, Thomas E. Booth, Jeremy Sweezy, R. A. Forster, Trevor Wilcox, Jeffrey S. Bull, Forrest B. Brown, Russell C. Johns, H. G. Hughes, Michael L Fensin, L. J. Cox, T. Zukaitis, Tim Goorley, Richard E. Prael, Laurie S. Waters, Gregg W. McKinney, Joe W. Durkee, Michael R. James, Stepan G. Mashnik, John S. Hendricks, Denise B. Pelowitz, Roger L. Martz
Publikováno v:
Nuclear Technology. 180:298-315
MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of those two computer codes. MCNP6 is the result of five years of effort by ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dd30f71d43f68ec8c90c949d500bee9b
https://doi.org/10.13182/nt11-135
https://doi.org/10.13182/nt11-135
Publikováno v:
Nuclear Technology. 170:68-79
Monte Carlo–linked depletion methods have gained recent interest due to the ability to model complex three-dimensional geometries using continuous-energy cross sections. The integration of CINDER90...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f4faab9c9598804e2f632aab5dfafcc
https://doi.org/10.13182/nt10-2
https://doi.org/10.13182/nt10-2
Publikováno v:
Nuclear Technology. 164:3-12
As advanced reactor concepts challenge the accuracy of current modeling technologies, a higher-fidelity depletion calculation is necessary to model time-dependent core reactivity properly for accurate cycle length and safety margin determinations. Th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f13a058541a525bd9c44a63fcc031d67
https://doi.org/10.13182/nt08-a4003
https://doi.org/10.13182/nt08-a4003