FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics

S.H. Ahn, N., Aksan, D. Bestion, B.D. Chung, F. D'Auria, P. Emonot, J.L. Gandrille, Markku Hänninen, I. Horvatovic, K.D. Kim, A. Kovtonyuk, A. Petruzzi

Research output: Contribution to journalArticleScientificpeer-review

11 Citations (Scopus)

Abstract

The 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 importance and value.In this framework the FONESYS initiative has been created. The main targets of FONESYS are:-To promote the use of SYS-TH Codes and the application of the BEPU approaches.-To establish acceptable and recognized procedures and thresholds for Verification and Validation (V&V).-To create a common ground for discussing envisaged improvements in various areas, including user-interface, and the connection with other numerical tools, including Computational Fluid Dynamics(CFD) Codes.
Original languageEnglish
Pages (from-to)103-113
JournalNuclear Engineering and Design
Volume281
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

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    Ahn, S. H., Aksan, N. ., Bestion, D., Chung, B. D., D'Auria, F., Emonot, P., Gandrille, J. L., Hänninen, M., Horvatovic, I., Kim, K. D., Kovtonyuk, A., & Petruzzi, A. (2015). FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics. Nuclear Engineering and Design, 281, 103-113. https://doi.org/10.1016/j.nucengdes.2014.12.001