共 50 条
- [12] NUMERICAL SIMULATION ON THE FLOW THROUGH THE INLET HOLE OF FUEL ASSEMBLY IN A FAST REACTOR PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 8, 2018,
- [15] Study on effect of flow blockage at inlet of plate-type fuel element on thermal-hydraulic characteristics of reactor core Hedongli Gongcheng/Nuclear Power Engineering, 2014, 35 (05): : 138 - 142
- [16] Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor International Journal of Advanced Nuclear Reactor Design and Technology, 2023, 5 (01): : 17 - 29
- [18] Development of Thermal-hydraulic Analysis Code for Spent Fuel Assembly of Sodium Cooled Fast Reactor Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2020, 54 (04): : 606 - 614
- [19] Design and neutronics characteristics analysis of the fuel assembly in gas-cooled fast reactor He Jishu/Nuclear Techniques, 2023, 46 (05):