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

7 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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nuclear reactors
Nuclear reactors
hydraulics
Hydraulics
reactor technology
User interfaces
Computational fluid dynamics
estimates
computational fluid dynamics
Hot Temperature
nuclear reactor
code
thresholds
Uncertainty

Cite this

Ahn, S. H., Aksan, N. ., Bestion, D., Chung, B. D., D'Auria, F., Emonot, P., ... 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
Ahn, S.H. ; Aksan, N., ; Bestion, D. ; Chung, B.D. ; D'Auria, F. ; Emonot, P. ; Gandrille, J.L. ; Hänninen, Markku ; Horvatovic, I. ; Kim, K.D. ; Kovtonyuk, A. ; Petruzzi, A. / FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics. In: Nuclear Engineering and Design. 2015 ; Vol. 281. pp. 103-113.
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title = "FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics",
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.",
author = "S.H. Ahn and N., Aksan and D. Bestion and B.D. Chung and F. D'Auria and P. Emonot and J.L. Gandrille and Markku H{\"a}nninen and I. Horvatovic and K.D. Kim and A. Kovtonyuk and A. Petruzzi",
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Ahn, SH, Aksan, N, Bestion, D, Chung, BD, D'Auria, F, Emonot, P, Gandrille, JL, Hänninen, M, Horvatovic, I, Kim, KD, Kovtonyuk, A & Petruzzi, A 2015, 'FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics', Nuclear Engineering and Design, vol. 281, pp. 103-113. https://doi.org/10.1016/j.nucengdes.2014.12.001

FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics. / Ahn, S.H.; Aksan, N.,; Bestion, D.; Chung, B.D.; D'Auria, F.; Emonot, P.; Gandrille, J.L.; Hänninen, Markku; Horvatovic, I.; Kim, K.D.; Kovtonyuk, A.; Petruzzi, A.

In: Nuclear Engineering and Design, Vol. 281, 2015, p. 103-113.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - FONESYS: The forum & network of system thermal-hydraulic codes in nuclear reactor thermal-hydraulics

AU - Ahn, S.H.

AU - Aksan, N.,

AU - Bestion, D.

AU - Chung, B.D.

AU - D'Auria, F.

AU - Emonot, P.

AU - Gandrille, J.L.

AU - Hänninen, Markku

AU - Horvatovic, I.

AU - Kim, K.D.

AU - Kovtonyuk, A.

AU - Petruzzi, A.

N1 - Project code: 81654

PY - 2015

Y1 - 2015

N2 - 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.

AB - 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.

U2 - 10.1016/j.nucengdes.2014.12.001

DO - 10.1016/j.nucengdes.2014.12.001

M3 - Article

VL - 281

SP - 103

EP - 113

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

ER -