This symposium is intended for numerical analysts and experimentalists to exchange information in nuclear reactor applications and systems related to computational fluid dynamics (CFD) activities. These include single-phase and multiphase applications in nuclear reactor-relevant issues such as pressurized thermal shock, critical heat flux, pool heat exchangers, boron dilution, hydrogen distribution, thermal mixing and stripping, among others. CFD codes contain empirical models for simulating turbulence, heat transfer, multiphase flows, and chemical reactions. Such models should be validated before they can be used with sufficient confidence in nuclear engineering applications. The necessary validation is performed by comparing model results against trustworthy data. A reliable model assessment requires CFD simulations with control of numerical errors to avoid erroneous conclusions being drawn concerning model performance. Manuscripts related to assessment, verification and validation are also encouraged.
| Lead Organizer: | Professor Koji Okamoto | The University of Tokyo | |
| Location: | Kashiwa | Chiba | Japan |
| Email: | okamoto@k.u-tokyo.ac.jp | ||
| Lead Organizer: | Professor Yassin Hassan | Texas A&M University | |
| Location: | College Station | TX | USA |
| Email: | y-hassan@tamu.edu | ||
| Lead Organizer: | Professor Ji Hwan JEONG | Pusan National University | |
| Location: | Busan | Korea | |
| Email: | jihwan@pusan.ac.kr | ||
| Organizer: | Dr. Jae Jun JEONG | Korea Atomic Energy Research Institute | |
| Location: | Daejeon | Korea | |
| Email: | jjjeong@kaeri.re.kr | ||