Zobrazeno 1 - 10
of 34
pro vyhledávání: '"Bousbia, Salah"'
Autor:
Foucaud, P., Di Giuli, M., Salmaoui, M., Bousbia Salah, A., Iglesias, R., Malkhasyan, A., Herranz, L.E.
Publikováno v:
In Annals of Nuclear Energy April 2024 198
Autor:
Bousbia Salah, A., Di Giuli, M., Foucaud, P., Iglesias, R., Malkhasyan, A., Salmaoui, M., Herranz, L.E.
Publikováno v:
In Annals of Nuclear Energy February 2024 196
Autor:
Bousbia-Salah, Anis, Benkharfia, Hocine, Kriangchaiporn, Nateekoool, Petruzzi, Alessandro, D’Auria, Francesco, Ghazi, Nidal
Publikováno v:
In Annals of Nuclear Energy 2008 35(5):845-855
Publikováno v:
In Annals of Nuclear Energy 2006 33(14):1164-1175
Publikováno v:
Annals of Nuclear Energy. 33:1164-1175
Optimization of neutron fluxes in experimental channels is of great concern in research reactor utilization. The general approach used at the NUR research reactor for neutron flux optimization in irradiation channels is presented. The approach is ess
Publikováno v:
Annals of Nuclear Energy. 33:646-652
Nowadays, the coupled codes technique, which consists in incorporating three-dimensional (3D) neutron modeling of the reactor core into system codes, is extensively used for carrying out best estimate (BE) simulation of complex transient in nuclear p
Autor:
Anis Bousbia-Salah, Tewfik Hamidouche
Publikováno v:
Annals of Nuclear Energy. 33:510-520
Best Estimate computer codes have been, so far, developed for safety analysis of nuclear power plants and were extensively validated against a large set of separate effects and integral test facilities experimental data relevant to such kind of react
Publikováno v:
Annals of Nuclear Energy. 33:405-414
During a loss of coolant accident leading to total emptying of the reactor pool, the decay heat could be removed through air natural convection. However, under partial pool emptying the core is partially submerged and the coolant circulation inside t
Autor:
Beniamino Di Maro, Francesco Saverio D'Auria, M. Adorni, F Pierro, Tewfik Hamidouche, Anis Bousbia-Salah
Publikováno v:
Annals of Nuclear Energy. 32:1679-1692
The main aim of the following study is to perform a safety analysis of the IAEA 10 MW MTR Pool type Research Reactor [IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uraniu
Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code
Publikováno v:
Annals of Nuclear Energy. 31:1385-1402
Nowadays, increased attention to safety issues for nuclear research reactors has emerged as a consequence of their enlarged commercial exploitation. Almost all of the research reactors safety analyses were, so far, performed using conservative comput