共 50 条
- [1] Study on Oxidation Corrosion Characteristics of Horizontal Lead-Bismuth Reactor Core Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (03): : 96 - 103
- [2] 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
- [3] Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor He Jishu/Nuclear Techniques, 2023, 46 (09):
- [4] A study on thermal hydraulic characteristics of fuel assembly by the subchannel code in small lead-bismuth reactor Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University, 2023, 44 (02): : 314 - 320
- [5] Experimental investigation on resistance characteristics of wire-wrapped fuel assembly in lead-bismuth eutectic Hedongli Gongcheng, 6 (27-31):
- [8] Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics He Jishu/Nuclear Techniques, 2024, 47 (11):
- [9] Investigation on numerical simulation models for heat transfer characteristics of lead-bismuth eutectic International Journal of Advanced Nuclear Reactor Design and Technology, 2024, 6 (01): : 57 - 66
- [10] Study on Jet Mixing Characteristics of Lead-Bismuth Eutectic Cooled Reactor Assembly Head Based on CFD Method Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (04): : 77 - 86