共 50 条
- [42] Simulation Model of a Passive Decay Heat Removal System for Lead-Cooled Fast Reactors JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2015, 137 (03):
- [43] Optimization of supercritical nuclear power system based on sodium cooled fast reactor THIRD INTERNATIONAL CONFERENCE ON ENERGY ENGINEERING AND ENVIRONMENTAL PROTECTION, 2019, 227
- [45] Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor Nuclear Science and Techniques, 2022, 33