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20 积分 2025-10-30 加入
Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors
2小时前
已完结
Determining the swelling of mixed nitride uranium-plutonium fuel based on the post-reactor studies of experimental BN-600 and BOR-60 fuel rods
9个月前
已完结
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