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- [42] Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (01): : 97 - 101
- [43] Diffusion and oxidation behavior of Cr-ZrN coated Zr alloy accident tolerant fuel cladding materials at high temperature SURFACE & COATINGS TECHNOLOGY, 2024, 476
- [47] Preliminary Analytical Study of the Effect of Accident Tolerant Fuel on Fuel Rod Performance under LOCA Condition Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (05): : 99 - 107