tThe purpose of this article is to present briefly the project called Forum & Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS), its participants, the motivation forthe project, its main targets and working modalities.System Thermal-Hydraulics (SYS-TH) codes, also as part of the Best Estimate Plus Uncertainty (BEPU)approaches, are expected to achieve a more-and-more relevant role in nuclear reactor technology, safetyand design. Namely, the number of code-users can easily be predicted to increase in the countries wherenuclear technology is exploited. Thus, the idea of establishing a forum and a network among the codedevelopers and with possible extension to code users has started to have major importa...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
A benchmark activity on two-phase critical flow (TPCF) prediction was conducted in the framework of ...
tThe purpose of this article is to present briefly the project called Forum & Network of System Ther...
The purpose of this article is to present briefly the project called Forum & Network of System T...
The nuclear reactor system thermal-hydraulic codes are extensively used in the safety analysis and i...
The paper provides a brief overview on the state of the art of the numerical modeling in present sys...
The paper provides a brief overview on the state of the art of the numerical modeling in present sys...
The purpose of the present article is to introduce the FONESYS, SILENCE and CONUSAF projects run by ...
International audienceThis paper introduces the FONESYS, SILENCE and CONUSAF projects run by some of...
The field of interest is nuclear thermal-hydraulics and whatever (as far as possible) in nuclear rea...
The purpose of this paper is to present briefly the projects called FONESYS (Forum & Network of Sys...
An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...
A benchmark activity on two-phase critical flow (TPCF) prediction was conducted in the framework of ...
An attempt is made to identify perspectives in nuclear thermal-hydraulics based on devoted papers pu...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
A benchmark activity on two-phase critical flow (TPCF) prediction was conducted in the framework of ...
tThe purpose of this article is to present briefly the project called Forum & Network of System Ther...
The purpose of this article is to present briefly the project called Forum & Network of System T...
The nuclear reactor system thermal-hydraulic codes are extensively used in the safety analysis and i...
The paper provides a brief overview on the state of the art of the numerical modeling in present sys...
The paper provides a brief overview on the state of the art of the numerical modeling in present sys...
The purpose of the present article is to introduce the FONESYS, SILENCE and CONUSAF projects run by ...
International audienceThis paper introduces the FONESYS, SILENCE and CONUSAF projects run by some of...
The field of interest is nuclear thermal-hydraulics and whatever (as far as possible) in nuclear rea...
The purpose of this paper is to present briefly the projects called FONESYS (Forum & Network of Sys...
An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...
A benchmark activity on two-phase critical flow (TPCF) prediction was conducted in the framework of ...
An attempt is made to identify perspectives in nuclear thermal-hydraulics based on devoted papers pu...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
A benchmark activity on two-phase critical flow (TPCF) prediction was conducted in the framework of ...