Molten salt reactor thorium fuel cyclic utilization method

A molten salt reactor and thorium fuel technology, applied in the direction of reactor fuel elements, reactor fuel materials, reactors, etc., can solve the problem of thorium fuel utilization scheme relying on online processing, etc., to suppress neutron absorption, increase fission contribution and reduce super The effect of the production of uranium

Inactive Publication Date: 2018-08-10
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0006] The technical problem to be solved by the present invention is to overcome the problem that the existing liquid fuel molten salt reactor thorium fuel utilization scheme relies on online processing technology, thereby providing a molten salt reactor thorium fuel recycling method that does not rely on online processing technology In this case, the fission contribution of thorium fuel in the molten salt reactor is increased, thereby increasing the utilization rate of U-235 and reducing the radioactivity and disposal amount of spent fuel

Method used

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  • Molten salt reactor thorium fuel cyclic utilization method
  • Molten salt reactor thorium fuel cyclic utilization method
  • Molten salt reactor thorium fuel cyclic utilization method

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Embodiment 1

[0031] Such as figure 1 As shown, the fuel molten salt of molten salt reactor 1 is LiF-BeF 2 -UF 4 -ThF 4 , the initial molar ratio is 70.0:18.0:1.0:6.0, the abundance of Li-7 is 99.995%, and the enrichment degree of uranium is 20%. The core of the molten salt reactor 1 adopts a graphite moderator module with a structural outline of a hexagonal prism. The distance between the sides of the module is 19.5 cm. The core is a cylinder with a diameter close to the height. The diameter of the cylinder is 5 m. The ratio to the total volume of the core is 5%.

[0032] During the operation of molten salt reactor 1, UF is continuously replenished 4 Fuel was fed at an average rate of 33 mol U / day / GWe to compensate for burnup reactivity, while fission gases were continuously removed by helium bubbling.

[0033] After 10 years of operation, the core spent fuel is put into the decay tank, and after cooling for 5 years, it enters the reprocessing system 2 for off-line processing. The fi...

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Abstract

The invention discloses a molten salt reactor thorium fuel cyclic utilization method. A reactor core comprises a graphite assembly and fuel molten salt, wherein the fuel molten salt is filled in a passage formed by the graphite assembly; the fuel molten salt comprises fuel salt and base salt; during operation, the on-line feeding is used; fission gas is cleared in a on-line way; reactor stopping off-line operation is performed, spent fuel is treated; recovered uranium, base salt and thorium are proportioned again and are then loaded into the reactor core for cyclic utilization, wherein the volume ratio of the fuel molten salt to the reactor core is 5 percent to 15 percent; the fuel salt is a mixture of ThF4 and UF4, wherein the U enrichment degree is 15 to 20 percent; the initial mole percentage of the fuel salt in the fuel molten salt is 6 percent to 8 percent; the initial mole percentage of ThF4 in the fuel salt is greater than 80 percent. The method has the advantages that under thecondition without depending an on-line treatment technology, the fission contribution of thorium fuel in the molten salt reactor is improved, so that the utilization rate of U-235 is improved; the radioactivity and the disposal quantity of the spent fuel are reduced.

Description

technical field [0001] The invention belongs to the field of nuclear reactor engineering design, in particular to a molten salt reactor thorium fuel recycling method. Background technique [0002] The geological storage of thorium is 3-4 times that of uranium. Thorium can be converted into fissile U-233 by absorbing a neutron. It is a potential nuclear fuel. The large-scale utilization of thorium will greatly expand nuclear fuel resources. reserves. At the same time, thorium fuel produces less highly radioactive transuranic elements and is a cleaner nuclear fuel. For this reason, there have been a large number of studies on the utilization of thorium in various nuclear reactors at home and abroad. [0003] Studies have shown that due to the limitation of the burnup depth of components in solid fuel reactors, the fuel conversion of thorium is not sufficient, and the improvement of fuel utilization is generally less than 20%. At the same time, it has a relatively large nega...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/54G21C19/28G21C19/50
CPCG21C3/54G21C19/28G21C19/50Y02E30/30
Inventor 朱贵凤邹杨邹春燕康旭忠陈金根严睿谈蒙露
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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