Zobrazeno 1 - 10
of 70
pro vyhledávání: '"Abderrafi M. Ougouag"'
Publikováno v:
Nuclear Science and Engineering. 196:v-vi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28abc5063d83a4aa070dbc736df39d45
https://doi.org/10.1080/00295639.2022.2105621
https://doi.org/10.1080/00295639.2022.2105621
Publikováno v:
Nuclear Engineering and Design. 344:174-182
The design and analysis of energy systems requires robust and reliable computer codes that produce realistic results. The governing equations and closure models must represent the physical behaviors of the energy systems. Nuclear power plants, as the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::985bddca0637315d3bbde55825516c68
https://doi.org/10.1016/j.nucengdes.2019.01.009
https://doi.org/10.1016/j.nucengdes.2019.01.009
Publikováno v:
Annals of Nuclear Energy. 145:105712
The swelling mechanisms of U3Si2 from neutron irradiation under power reactor conditions are not unequivocally known. The limited experimental evidence that is available suggests that the main driver for swelling in this material would be fission gas
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35ea933236dc5075ad5e94c0bea2fd8d
https://doi.org/10.1016/j.anucene.2017.08.045
https://doi.org/10.1016/j.anucene.2017.08.045
Publikováno v:
Annals of Nuclear Energy. 63:751-762
A multi-group formulation for the exact neutron elastic scattering kernel is developed. It incorporates the neutron up-scattering effects stemming from lattice atoms thermal motion and it accounts for them within the resulting effective nuclear cross
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7b0b32719c9a2b79d46d42fdf0e67be4
https://doi.org/10.1016/j.anucene.2013.07.031
https://doi.org/10.1016/j.anucene.2013.07.031
Autor:
Mie Hiruta, Gannon Johnson, Maziar Rostamian, Gabriel P. Potirniche, Abderrafi M. Ougouag, Massimo Bertino, Louis Franzel, Akira Tokuhiro
Publikováno v:
Nuclear Engineering and Design. 263:509-514
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7b442149ff41d9dc1c2f3a6b785be27e
https://doi.org/10.1016/j.nucengdes.2013.04.032
https://doi.org/10.1016/j.nucengdes.2013.04.032
Publikováno v:
Scopus-Elsevier
A local incident flux response expansion transport method is developed to generate transport solutions for coupling to diffusion theory codes regardless of their solution method (e.g., fine mesh, nodal, response based, finite element, etc.) for react
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3a0f49a81a4af4dc30a7eff148ae22f7
https://doi.org/10.13182/nse12-61
https://doi.org/10.13182/nse12-61
Publikováno v:
Nuclear Engineering and Design. 255:310-320
The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with failure-proof fuel. This paper examines the feasibility of LWR-like cycle length for such fuel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e77de4e160e833d62d5eb343d4d139e
https://doi.org/10.1016/j.nucengdes.2012.11.007
https://doi.org/10.1016/j.nucengdes.2012.11.007
Publikováno v:
Nuclear Engineering and Design. 252:215-225
Calculations are performed to assess the neutronic behavior of fully ceramic micro-encapsulated (FCM) fuel in otherwise-conventional pressurized water reactor (PWR) fuel pins. The FCM fuel contains transuranic (TRU) oxide fuel, solely, encapsulated i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::694caef08eaac7cbb8c639541d946156
https://doi.org/10.1016/j.nucengdes.2012.07.013
https://doi.org/10.1016/j.nucengdes.2012.07.013
Publikováno v:
Nuclear Engineering and Design. 243:33-40
This paper describes the computational modeling and simulation of graphite pebbles in frictional contacts as anticipated in a pebble bed reactor. For the high temperature gas-cooled reactor, the potential dust generation from frictional contact at th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4cb703a938a512c70cd0b0aae68add73
https://doi.org/10.1016/j.nucengdes.2011.12.011
https://doi.org/10.1016/j.nucengdes.2011.12.011
Publikováno v:
Nuclear Engineering and Design. 241:5018-5032
The dominating mechanism in the passive safety of gas-cooled, graphite-moderated, high-temperature reactors (HTRs) is the Doppler feedback effect. These reactor designs are fueled with submillimeter-sized kernels formed into tristructural-isotropic (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::228c18c8339d60ee34580d663469c9a7
https://doi.org/10.1016/j.nucengdes.2011.08.072
https://doi.org/10.1016/j.nucengdes.2011.08.072