Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Bousbia, Salah"'
Autor:
Alexander Grahn, S. C. Ceuca, H. Austregesilo, Jacques Vlassenbroeck, Sören Kliem, R. Puragliesi, Roman Mukin, A. Bousbia Salah
Publikováno v:
Nuclear Technology. 203:293-314
Advanced three-dimensional (3-D) computational tools are increasingly being used to simulate complex phenomena occurring during scenarios involving operational transients and accidents in nuclear power plants. Among these scenarios, one can mention t
Autor:
Anis Bousbia-Salah
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 22, Iss 1, Pp 18-33 (2007)
Complex phenomena, as water hammer transients, occurring in nuclear power plants are still not very well investigated by the current best estimate computational tools. Within this frame work, a rapid positive reactivity addition into the core generat
Publikováno v:
Progress in Nuclear Energy. 49:1-13
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the design, safety and the operation of Light Water Nuclear Reactors (LWR). The lack of full understanding of complex mechanisms related to the interaction
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
Autor:
Areeya Jirapongmed, John R. White, Anis Bousbia-Salah, Francesco Saverio D'Auria, M. Adorni, Tewfik Hamidouche
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 21, Iss 1, Pp 3-12 (2006)
RELAP5 is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. Howeve
Autor:
Francesko D'auria, Anis Bousbia-Salah
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 17, Iss 1-2, Pp 44-49 (2002)
This paper presents the results of the application of the system of the thermalhydraulic code RELAP5/Mod3.2 in predicting the Peach Bottom Boiling Water Reactor Turbine Trip test. This experiment constitutes a challenge to the capabilities of current
Publikováno v:
Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications.
This paper investigates the possibility to extend standard computer tools and methods, commonly used in the safety technology of nuclear power reactors, to research reactor safety analysis. A 3-D Neutron Kinetics Thermal-Hydraulic code (3D-NKTH), bas
Autor:
Francesco Saverio D'Auria, Soeren Kliem, Ulrich Rohde, Anis Bousbia Salah, Alessandro Petruzzi
Publikováno v:
Nuclear Engineering and Design 236(2006), 1240-1255
The modeling of complex transients in nuclear power plants (NPP) remains a challenging topic for best estimate three-dimensional coupled code computational tools. This technique is, nowadays, extensively used since it allows decreasing conservatism i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c47e5dccb903f046c0176cd3779c32b4
http://hdl.handle.net/11568/100596
http://hdl.handle.net/11568/100596