文章名稱引用次數

• FUEL PIN MELTING IN A FAST REACTOR AND MELT SOLIDIFICATION: SIMULATION USING THE SAFR/V1 MODULE OF THE EVKLID/V2 INTEGRAL CODE4
• Nuclear Problems of Thermonuclear Power Generation3
• SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident2
• Purification of Regenerated Uranium Hexafluoride by Removal of U-U-U-236 in the Intermediate Product of a Two-Feed-Flow Cascade2
• Radiolysis of U-U-234-Enriched Regenerated-Uranium Hexafluoride at the Temporary Storage Stage in a Separation Plant2
• Neptunium-Based High-Flux Pulsed Research Reactor2
• MECHANISM OF CHANGE IN VVER--1000 VESSEL MATERIAL PROPERTIES IN IRRADIATION-RECOVERY ANNEALING-IRRADIATION CYCLE2
• Possibility of Increasing the Number of Experimental Channels in VVR-Ts by Changing the Core Design1
• Economic Efficiency of Bringing Depleted Uranium into Enrichment1
• MODERATE-BREEDING FAST REACTORS AND THE STRUCTURE OF NUCLEAR POWER1