Method for reconstructing molten salt reactor fuel

• Main Authors: LI QINGNUAN, WANG PENG, NIU YONGSHENG, LIN JUN, DOU QIANG, HU CONGWEI, SUN LIXIN, CAO CHANGQING
• Format: Patent
• Language: Chinese; English
• Published: 16.04.2019
• Subjects: NUCLEAR ENGINEERING; NUCLEAR PHYSICS; NUCLEAR REACTORS; PHYSICS

The invention provides a method for reconstructing molten salt reactor fuel. The method comprises the following steps that S1, molten fluoride fused salt containing uranium tetrafluoride is provided;S2, active metal is provided, active metal is oxidized into metal ions in the fluoride fused salt through a redox reactor, and meanwhile, the uranium tetrafluoride is reduced into uranium trifluoride;S3, mixed gas of uranium hexafluoride and inert gas is introduced into the fluoride fused salt, so that the uranium hexafluoride and the uranium trifluoride are subjected to a redox reactor to generate uranium tetrafluoride, and a uranium material in the fluoride fused salt is reconstructed. Particularly, when the method is used for reconstructing thorium-based fused salt reactor fuel, the uranium material and a thorium material can be reconstructed at the same time. According to the method, the method which is used for reconstructing the molten salt reactor fuel, is simple in process and inequipment cost, prevents eq