Separation purification method of radioactive electrolysis waste salt
A radioactive and molten salt electrolysis technology, applied in vacuum distillation and other directions, can solve the problems of experimental devices lacking engineering application conditions, etc., and achieve the effect of simple and easy process, high efficiency and reduced volume
Inactive Publication Date: 2019-05-17
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology
At present, domestic research on molten salt distillation of radioactive waste salt is still in a blank state, and there is a lack of experimental devices with engineering application conditions.
Method used
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Embodiment 1
[0047] Put 200g pre-mixed NaCl-KCl-CeO 2 -CeCl 3 The simulated salt (wherein the mass fraction of NaCl-KCl is 85%) is loaded into the evaporation crucible 6 . Use the lifting device 14 to raise and close the distillation cabin airtight door 13 as a whole.
[0048] Start the vacuum pump 1, slowly open the valve 3, fully open the valve 3 after 2 to 3 minutes, continue to evacuate, and keep the pressure in the distillation chamber 9 at the ultimate vacuum state (about 0.1Pa).
[0049] Set the heating programs for the upper space, the middle space and the lower space respectively, such as image 3 shown. The heating program is divided into four insulation sections:
[0050] The first section is the heat preservation and dehydration stage, and the purpose is to remove a small amount of moisture that may exist in the distillation cabin 9 and the raw material;
[0051] The second stage is the constant temperature heating stage, the purpose is to reduce the temperature difference...
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The invention belongs to the technical field of radioactive waste treatment, and relates to a separation purification method of radioactive electrolysis waste salt. The separation purification methodis characterized in that the radioactive electrolysis waste salt generated by a nuclear material molten salt electrolysis process is added into an evaporation crucible in a distillation cabin for vacuum heating distillation; molten salt ingredients obtained through distillation are collected in a collecting crucible in the distillation cabin; the inside space of the distillation cabin is divided into an upper space, a middle space and a lower space; the evaporation crucible is arranged in the upper space; the collecting crucible is arranged in the lower space; in the vacuum heating distillation process, the upper space, the middle space and the lower space use different temperature rise program, so that the temperature gradient that the temperature is gradually reduced from top to bottom is formed in the distillation cabin. When the separation purification method is used, radioactive substances and molten salt ingredients in the radioactive electrolysis waste salt generated by the nuclear material molten salt electrolysis process can be effectively separated.
Description
technical field [0001] The invention belongs to the technical field of radioactive waste treatment, and relates to a method for separating and purifying radioactive electrolytic waste salt. Background technique [0002] A large amount of chloride molten salt is used as the electrolyte in the molten salt electrolysis process of nuclear materials such as uranium and plutonium. The molten salt component is usually an alkali metal chloride such as LiCl-KCl or NaCl-KCl. After a certain period of use, due to the increase of impurity elements, the molten salt used in electrolysis must be replaced to ensure the stability of the electrolysis process. These replaced waste salts are highly radioactive and cannot meet the disposal standards for low-level waste (LLW) and need to be disposed of. [0003] Molten salt distillation separation process is an effective process to deal with these radioactive waste salts. In the process, the vapor pressure of the basic component of chlorine sal...
Claims
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IPC IPC(8): B01D3/10
Inventor 李迅叶国安何辉贾艳虹林如山
Owner CHINA INSTITUTE OF ATOMIC ENERGY