共 50 条
- [1] Thermal-hydraulic Simulation and Steam Cavity Diffusion of SGTR Accident in Lead-cooled Fast Reactor Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (10): : 2015 - 2023
- [3] The Simulation of Thermal Hydraulic of the Lead-Cooled Fast Reactor PROCEEDINGS OF THE 20TH PACIFIC BASIN NUCLEAR CONFERENCE, VOL 1, 2017, : 739 - 747
- [4] Analysis of Transient Thermal-Hydraulic and Safety of Lead-Cooled Fast Reactor Based on Unified Coupling Framework Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 : 11 - 16
- [5] NUMERICAL INVESTIGATION OF POSTUATED STEAM GENERATOR TUBE RUPTURE ACCIDENT IN A LEAD-COOLED FAST REACTOR PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
- [7] EFFECT OF DIFFERENT P/D RATIOS ON THE THERMAL-HYDRAULIC PERFORMANCE OF FUEL ASSEMBLIES IN A LEAD-COOLED FAST REACTOR PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 7, ICONE31 2024, 2024,
- [9] Void Transport after Steam Generator Tube Leakage in Natural Circulation Lead-cooled Fast Reactor Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2020, 54 (12): : 2344 - 2352