, 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.
FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics, Nuclear Engineering and Design, vol.281, pp.103-113, 2015. ,
FONESYS and SILENCE Networks: Looking to the Future of T-H Code Development and Experimentation, Proceedings of the 24 th International Conference Nuclear Energy for New Europe (NENE2015), 2015. ,
, Significant Light and Heavy Water Reactor Thermal Hydraulic Experiments Network for the Consistent Exploitation of the Data (SILENCE)
The effects of complexity, of simplicity and of scaling in thermal-hydraulics, Nuclear Engineering and Design, vol.204, pp.1-27, 2001. ,
Critical review of conservation equations for two-phase flow in the U.S. NRC TRACE code, Nuclear Engineering and Design, vol.241, pp.4237-4260, 2011. ,
Current use of Best Estimate plus Uncertainty methods on operational procedures addressing normal and emergency conditions, EUR 23717 EN, 2008. ,
Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view, Nuclear Engineering and Design, vol.322, pp.227-239, 2017. ,
, Proceedings of the OECD/CSNI Specialist Meeting on Advanced Instrumentation and Measurement Techniques, p.33, 1997.
, 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
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. ,
Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal Hydraulics Experimentation, Special issue of Nuclear Engineering and Design, 2018. ,
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. ,
Moving from V&V to V&V&C in Nuclear Thermal-Hydraulics, 2018. ,
Introducing V&V&C in Nuclear Thermal-Hydraulics, Submitted to ASME 2018 Verification and Validation Symposium, 2018. ,