SIMULATION OF SPACER GRID WITH MIXING VANE ON A TYPICAL PWR FUEL ROD BUNDLE SYSTEM USING LATTICE BOLTZMANN METHOD
Yazarlar (2)
Doç. Dr. Ali TİFTİKÇİ Sinop Üniversitesi, Türkiye
Prof. Dr. Cemil Kocar Hacettepe Üniversitesi, Türkiye
| Bildiri Türü | Tebliğ/Bildiri | Bildiri Dili | İngilizce |
| Bildiri Alt Türü | Tam Metin Olarak Yayınlanan Tebliğ (Uluslararası Kongre/Sempozyum) | ||
| Bildiri Niteliği | Alanında Hakemli Uluslararası Kongre/Sempozyum | ||
| Kongre Adı | The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 | ||
| Kongre Tarihi | 12-05-2013 / 17-05-2013 | ||
| Basıldığı Ülke | İtalya | Basıldığı Şehir | Pisa |
| UAK Araştırma Alanları |
Reaktör Teknolojisi
|
||
| Özet |
| In present paper, the effect of spacer grid on adiabatic single phase flow in a typical nuclear reactor fuel assembly is investigated. Spacer grid with mixing vane of PWR subchannel is simulated. Velocity and pressure profiles for flow around the spacer grid and fuel rod are analysed. Simulation results of 2x2 Pressurized Water Reactor (PWR) rod bundle system with spacer grids and mixing vane are presented. The simulations have been carried out using lattice-Boltzmann method. Flow regime in flow channel is assumed to be laminar and the rod bundle system geometry is nearly realistic. This work offers an alternative way to model nuclear reactor rod bundle system which is the subject of many studies for researchers in order to determine reactor thermal margin and safety. In the near future, turbulent flow regime and heat transfer mechanisms will be adapted to this work. |
| Anahtar Kelimeler |
