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Method and system for producing high-activity-ratio Sr-89 and Sr-90 through liquid molten salt reactor

A SR-90, molten salt reactor technology, applied in the direction of reactor fuel material, reactor/accelerator external conversion, reduction of greenhouse gases, etc., can solve the problems of low production efficiency, high economic cost, low activity ratio, etc.

Active Publication Date: 2021-05-28
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] The purpose of the present invention is to provide a method and system for producing high activity ratio Sr-89 and Sr-90 in a liquid molten salt reactor, thereby solving the problem of producing Sr-89 and Sr-90 by irradiating solid targets in the prior art Low activity ratio, low production efficiency, difficult chemical technology, high economic cost, etc.

Method used

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  • Method and system for producing high-activity-ratio Sr-89 and Sr-90 through liquid molten salt reactor
  • Method and system for producing high-activity-ratio Sr-89 and Sr-90 through liquid molten salt reactor
  • Method and system for producing high-activity-ratio Sr-89 and Sr-90 through liquid molten salt reactor

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Embodiment

[0042] A molten salt composed of low-enrichment uranium and base salt is filled in the channel 4 of the graphite moderator component 3 , and the volume ratio of the molten salt to the graphite moderator component 3 is 1:5. Start the liquid molten salt reactor. During operation, the solid fission products are separated and recovered through the gas-liquid separation device in the bypass. The flow period of the molten salt in the bypass is 100s, and the gas-liquid separation efficiency is 95%. Collect uranium to maintain the reactor criticality at 1. The cooling time of the gas fission product in the cooling tank 1 is 6 minutes. The gas Kr-90 decays to generate solid Rb-90 and then produces Sr-90. The separation efficiency of Sr from the solid fission product is 90%. A 2MW liquid fuel molten salt reactor It can produce about 2000Ci of Sr-90 every year. Then blow the gas from the cooling tank 1 into the cooling tank 2, the cooling time is 100 minutes, then the annual production ...

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Abstract

The invention discloses a method and a system for producing Sr-89 and Sr-90 with high activity ratios by using a liquid molten salt reactor. The method comprises the following steps: providing a liquid molten salt reactor provided with a plurality of graphite moderation assemblies, wherein Kr-89 and Kr-90 are directly generated in a fission manner when the reactor runs, a gas fission product Kr is separated from the molten salt reactor by using a blowing method, a cooling method is adopted for decaying gas Kr-90 and a sub-product Rb-90 of the gas Kr-90 to produce solid Sr-90, then a blowing method is adopted for separating residual gas Kr from solid Sr, and then a cooling method is adopted for decaying gas Kr-89 and a sub-product Rb-89 of the gas Kr-89 to produce solid Sr-89, and finally, chemical separation is adopted for respectively extracting so as to realize preparation of Sr-89 and Sr-90 with high activity ratios. According to the method and the system for producing the Sr-89 and the Sr-90 by the liquid molten salt reactor, provided by the invention, the production efficiency is improved, the operation is convenient and fast, and the economic cost is low.

Description

technical field [0001] The invention relates to the field of nuclear reactor engineering and nuclear technology application, and more specifically relates to a method and a system for producing high activity ratio Sr-89 and Sr-90 in a liquid molten salt reactor. Background technique [0002] Sr-89 is one of the important radioisotopes for the treatment of bone cancer metastasis. Sr-89 is pure β decay (the maximum decay energy is 1492.1keV), and the half-life is (50.5d). Sr-89 is an alkaline earth element, its chemical properties are similar to Ca, and it has a high affinity for metabolically active bone. After intravenous injection, it will selectively concentrate on the site of increased osteogenic activity. Sr-89 is absorbed into the mineral structure of the bone, the metabolism of the diseased bone will not take place, while the healthy bone will metabolize the injected dose within two weeks. The free path of β particles of Sr-89 in bone tissue does not exceed 7mm, and ...

Claims

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Application Information

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IPC IPC(8): G21G1/08G21C3/54
CPCG21G1/08G21C3/54Y02E30/30
Inventor 余呈刚吴辰邹春燕王小鹤陈金根邹杨蔡翔舟
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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