FONESYS: The FOrum &amp; NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

Ahn, Seung Hoon; Aksan, N.; Austregesilo, H.; Bestion, D.; Chung, Bub Dong; D'Auria, Francesco Saverio; Emonot, Philippe; Gandrille, J.L.; Hänninen, Markku; Horvatovic, I.; Kim, K. D.; Kovtonyuk, A.; Petruzzi, A.

doi:10.1016/j.nucengdes.2014.12.001

Cited by 19 publications

(3 citation statements)

References 6 publications

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“…The coding system enables a consistent multi-physics and multiscale examination of operational and emergency regimes to be carried out. Ahn et al [ 85 ] report on the FONESYS code to support code users in the nuclear industry. As a result, they established a forum and network for programmers as users.…”

Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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“…System thermal hydraulic code-developers who are members of the FONESYS, [24], decided to compare CHF code predictions referring to an assigned fuel assembly. Different codes simulated an imposed flow-decrease transient starting from nominal operation.…”

Section: Chf T-hp 47 In Tablementioning

confidence: 99%

Physical Phenomena in Nuclear Thermal Hydraulics and Current Status

D'Auria¹,

Aksan²,

Glaeser³

2021

TI-IJES

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116 nuclear Thermal-Hydraulic Phenomena T-HP are identified in the present paper, following documents issued during the last three decades by the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA/CSNI) and by the International Atomic Energy Agency (IAEA). The derived T-HP list includes consideration of experiments performed in Separate Effect Test (SET) and Integral Effect Test (IET) facilities relevant to reactor coolant system and containment of Water Cooled Nuclear Reactors (WCNR). We consider a dozen WCNR types: Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR), Russian reactors (VVER-440, VVER-1000 and RBMK), pressure tube heavy water reactors by Canada (CANDU) and India (PHWR) and so-called ‘advanced’ reactors (e.g. AP-1000 and APR-1400 designed in US and Korea, respectively). We envisage a variety of applications for the T-HP list. Four of the phenomena are helpful to characterize the current state of art in nuclear thermal-hydraulics: Counter Current Flow Limitation (CCFL), Critical Heat Flux (CHF), reflood and Two-Phase Critical Flow (TPCF). Furthermore, the T-HP identification contributes to addressing the scaling issue, performing uncertainty evaluations, developing constitutive equations and ‘special models’ in codes and prioritizing the research.

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“…Considering the above, a benchmark activity on TPCF prediction was started in 2015 within the Forum & Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS) (Lanfredini and Lutsanych, 2020). Launched in May of 2010 upon initiative of the University of Pisa, the FONESYS Network is connecting international organizations and institutions active in the area of nuclear SYS-TH codes development (Ahn et al, 2015;Aksan et al, 2018;FONESYS, 2020).…”

Section: Introductionmentioning

confidence: 99%

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

Lanfredini

Bestion²,

D'Auria

et al. 2020

Nuclear Engineering and Design

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FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

Cited by 19 publications

References 6 publications

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Physical Phenomena in Nuclear Thermal Hydraulics and Current Status

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

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