Zobrazeno 1 - 10 of 101 pro vyhledávání: '"A.L. Aronson"'
1
TRACE/PARCS Analysis of Anticipated Transient Without Scram with Instability for a MELLLA+ BWR/5
Autor: P. Yarsky, J. S. Baek, A.L. Aronson, David J. Diamond, A. Cuadra, Lap-Yan Cheng
Publikováno v: Nuclear Technology. 196:238-247
A TRACE/PARCS model has been developed to analyze anticipated transient without SCRAM (ATWS) events for a boiling water reactor (BWR) operating in the maximum extended load line limit analysis-plus (MELLLA+) expanded operating domain. The MELLLA+ dom
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0d5c7656a67d51a7f3349e77eeab3125
https://doi.org/10.13182/nt16-29
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2
Neutronic performance of uranium nitride composite fuels in a PWR
Autor: A.L. Aronson, Nicholas R. Brown, Ryan A. Brito, Michael Todosow, Kenneth J. McClellan
Publikováno v: Nuclear Engineering and Design. 275:393-407
Uranium mononitride (UN) based composite nuclear fuels may have potential benefits in light water reactor applications, including enhanced thermal conductivity and increased fuel density. However, uranium nitride reacts chemically when in contact wit
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::aa779d75e4f5ab4e2c2cba1f47cc01aa
https://doi.org/10.1016/j.nucengdes.2014.04.040
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3
Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients
Autor: Gilad Raitses, Michael Todosow, Hans Ludewig, A.L. Aronson, Nicholas R. Brown
Publikováno v: Annals of Nuclear Energy. 62:538-547
The fully ceramic microencapsulated (FCM) fuel concept is based on the tri-isotropic (TRISO) carbon coated fuel particles. These particles were developed and demonstrated for use in high temperature gas reactors. It has been proposed to use these par
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ebcf9d04313730add0066fd662d2a56f
https://doi.org/10.1016/j.anucene.2013.05.025
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4
Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback
Autor: Gilad Raitses, Nicholas R. Brown, A.L. Aronson, Hans Ludewig, Michael Todosow
Publikováno v: Annals of Nuclear Energy. 62:548-557
The fully ceramic microencapsulated (FCM) fuel is based on the tri-isotropic (TRISO) carbon coated fuel particles. These particles were developed and demonstrated for use in high temperature gas reactors. It has been proposed to use these particles i
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::11ea67d10540e3de8bed12dfd9f5b643
https://doi.org/10.1016/j.anucene.2013.05.027
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6
Thorium fuel cycles with externally driven systems
Autor: A.L. Aronson, Gilad Raitses, Massimiliano Fratoni, Michael Todosow, Eva E Sunny, Jeffrey J. Powers, Hans Ludewig, Nicholas R. Brown
Publikováno v: Nuclear Technology, vol 194, iss 2
Brown, NR; Powers, JJ; Todosow, M; Fratoni, M; Ludewig, H; Sunny, EE; et al.(2016). Thorium fuel cycles with externally driven systems. Nuclear Technology, 194(2), 233-251. doi: 10.13182/NT15-40. UC Berkeley: Retrieved from: http://www.escholarship.org/uc/item/69b7v458
© 2016, American Nuclear Society. All rights reserved. Externally driven subcritical systems are closely associated with thorium, partially because thorium has no naturally occurring fissile isotopes. Both accelerator-driven systems (ADSs) and fusio
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::75f513df313c9fbff7bbff9447997f86
https://escholarship.org/uc/item/69b7v458
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7
Intercomparison of results for a PWR rod ejection accident
Autor: A.L. Aronson, D.J. Diamond, M.E. Royer, V. Malofeev, A. Avvakumov, P. Ferraresi, S. Aniel, V. Sidorov, J. Jo, C. Gouin
Publikováno v: Nuclear Engineering and Design. 208:181-189
This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1e71d10251240b6b8b12d6d14f0dce9f
https://doi.org/10.1016/s0029-5493(01)00375-2
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8
Incineration of Radioactive Fission Products and Transuranics by Muon-Catalyzed Fusion
Autor: Nobuyuki Sasao, A.L. Aronson, Hideo Harada, Takeshi Kase, Hiroshi Takahashi, Kenji Konashi
Publikováno v: Fusion Technology. 24:161-167
A system of nuclear transmutation is presented in which fission products and transuranics (TRU) are incinerated using 14-MeV neutrons produced by muon-catalyzed fusion ([mu]CF) and a subcritical core composed of fission products and TRU. The 14-MeV n
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5d9d78de02e7f1db91743cbf1479f971
https://doi.org/10.13182/fst93-a30222
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10
Analyses of Unscrammed Events Postulated for the Prism Design
Autor: A.L. Aronson, G.C. Slovik, R.J. Kennett, B.C. Chan, Gregory J. Van Tuyle
Publikováno v: Nuclear Technology. 91:165-184
Analytical results from an independent evaluation of the so-called “inherent reactor shutdown” mechanism in the proposed Power Reactor Inherently Safe Module (PRISM) advanced liquid-metal reactor d...
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::dfc246d27cded63afac2d5390d1360d6
https://doi.org/10.13182/nt90-a34426
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