, State of the art 6.2. Modelling turbulent diffusion and dispersion in porous medium 6.3. Validation for core, downcomer, lower plenum, upper plenum, CFD IN POROUS MEDIUM approach 6.1

, CFD IN OPEN MEDIUM approach 7.1. State of the art in 1-phase and in 2 phases 7.2. Support of CFD for modelling and validating system codes and component codes: 7.2.1. Core mixing of temperature

, VALIDATION AND EXPERIMENT 8.1. Identifying new needs 8.2. Requirements for experiments 8.3. Multi-scale validation: e.g. using CFD for validating system codes 8.4. Defining common experimental programs and sharing data 8.5. New ideas for validation strategies

, New safety barriers 10.4. Sharing experiences, applications, "chains of adopted codes" 11. COUPLING 11.1. State of the art 11.2. Coupling between different codes (SYS-TH, fuel performance, CFD, 3DNK, containment, structural mechanics, I&C, etc.) 11.2.1. Numerical aspects and physical aspects 11.3. Coupling interfaces (e.g. in-house tools, PVM, etc.) 11.4. Coupling verification and validation Containment and subchannel codes are, SAFETY ANALYSES 10.1. State of the art 10.2. (New) BEPU methodologies, risk informed, vol.10

, The list of areas is supposed to be a "living document

, and was attended by eighteen Organizations coming from Europe, United States of America, Canada and Asia. A specific session was devoted to collecting topics of main interest, current issues as well as suggestions from the Participants REFERENCES 1, The Kick-Off Meeting was held in Texas A&M University, 2017.

S. H. Ahn, N. Aksan, H. Austregesilo, D. Bestion, B. D. Chung et al., FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics, Nuclear Engineering and Design, vol.281, pp.103-113, 2015.

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, Significant Light and Heavy Water Reactor Thermal Hydraulic Experiments Network for the Consistent Exploitation of the Data (SILENCE)

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S. H. Ahn, N. Aksan, H. Austregesilo, D. Bestion, B. D. Chung et al., Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view, Nuclear Engineering and Design, vol.322, pp.227-239, 2017.

. Oecd/nea/csni, Proceedings of the OECD/CSNI Specialist Meeting on Advanced Instrumentation and Measurement Techniques, p.33, 1997.

. Oecd/nea/csni, Summary and Conclusions of the OECD/CSNI Specialist Meeting on Advanced Instrumentation and Measurement Techniques, p.32, 1997.

, SWINTH-2016 -Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal Hydraulics

F. Moretti, F. Auria, N. Aksan, S. Lutsanych, K. Umminger et al., Summary Of Swinth-2016: A Specialists Workshop On Advanced Instrumentation And Measurement Techniques For Nuclear Reactor Thermal-Hydraulics Experimentation, Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Qujiang Int'l Conference Center, 2017.

N. Aksan, D. Bestion, F. Auria, Y. Hassan, and F. Moretti, Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal Hydraulics Experimentation, Special issue of Nuclear Engineering and Design, 2018.

. Oecd/nea/csni/wgama, Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), CAPS approved on, 2018.

F. and M. Lanfredini, Moving from V&V to V&V&C in Nuclear Thermal-Hydraulics, 2018.

F. and M. Lanfredini, Introducing V&V&C in Nuclear Thermal-Hydraulics, Submitted to ASME 2018 Verification and Validation Symposium, 2018.