Method for recycling NH3-N from ammoninted waste liquid

A recovery method and low-radioactivity technology, which is applied in the field of waste liquid treatment, can solve problems such as pollution, radioactive substances escaping, and increased energy consumption, and achieve the effects of compact process flow, reduced water replenishment, and improved recovery rate

Active Publication Date: 2014-05-07
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

The stripping method is easy to produce a large amount of radioactive waste gas when dealing with low-radioactive ammonia-containing waste liquid, which will increase the energy consumption and form new pollution in the application; if the conventional distillation method can not control the heating conditions well, it will occur during the heating process. The rapid release of ammonia gas produces a large amount of mist entrainment, resulting in the escape of radioactive materials
Therefore, there is still a lack of an effective treatment of high-concentration NH 3 -N low-level radioactive waste liquid process

Method used

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  • Method for recycling NH3-N from ammoninted waste liquid

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Effect test

Embodiment 1

[0034] During the production of a batch of fuel elements, about 250 liters of ammonia-containing process waste liquid needs to be treated. NH in raw water 3 -N mass concentration is 8.9%, the main radioactive substance is uranium 235, the concentration is about 10ppm. In order to realize the removal and recovery of ammonia in wastewater and avoid the secondary pollution of radioactive uranium 235, the mode of intermittent heating and intermittent feeding is used to recover ammonia by distillation. The whole process is shown in figure 1 As shown, the specific process is as follows:

[0035] (1) The ammonia-containing process waste liquid is left standing in the waste liquid tank. After the solid matter in the waste liquid is precipitated, the supernatant liquid is sent to the heat exchanger by a pump. After heat exchange to increase the temperature, it is pumped into the evaporator for heating.

[0036] (2) First pump two-thirds of the volume of feed liquid into the evaporatin...

Embodiment 2

[0042]During the production of a certain batch of fuel elements, about 200 liters of ammonia-containing process waste liquid needs to be treated. NH in raw water 3 -N mass concentration is 5.3%, the main radioactive substance is uranium 235, the concentration is about 10ppm. In order to realize the removal and recovery of ammonia in wastewater and avoid the secondary pollution of radioactive uranium 235, the mode of intermittent heating and intermittent feeding is used to recover ammonia by distillation. The whole process is shown in figure 1 As shown, the specific process is as follows:

[0043] (1) The ammonia-containing process waste liquid is left standing in the waste liquid tank. After the solid matter in the waste liquid is precipitated, the supernatant liquid is sent to the heat exchanger by a pump. After heat exchange to increase the temperature, it is pumped into the evaporator for heating.

[0044] (2) First pump two-thirds of the volume of feed liquid into the eva...

Embodiment 3

[0050] During the production of a certain batch of fuel elements, about 200 liters of ammonia-containing process waste liquid needs to be treated. NH in raw water 3 -N mass concentration is 7.8%, the main radioactive substance is uranium 235, the concentration is about 10ppm. In order to realize the removal and recovery of ammonia in wastewater and avoid the secondary pollution of radioactive uranium 235, the mode of intermittent heating and intermittent feeding is used to recover ammonia by distillation. The whole process is shown in figure 1 As shown, the specific process is as follows:

[0051] (1) The ammonia-containing process waste liquid is left standing in the waste liquid tank. After the solid matter in the waste liquid is precipitated, the supernatant liquid is sent to the heat exchanger by a pump. After heat exchange to increase the temperature, it is pumped into the evaporator for heating.

[0052] (2) First pump one-third of the volume of feed liquid into the eva...

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Abstract

The invention provides a method for recycling NH3-N from ammoninted waste liquid, and further provides a method for recycling NH3-N from ammoninted waste liquid with low radioactivity and high concentration. The method comprises the following steps of: based on an intermittent feeding mode, evaporating and condensing waste liquid; and repeatedly absorbing NH3-N to recycle NH3-N from the waste liquid, wherein the final mass concentration of ammonia water can reach about 15%. The method is low in energy consumption, capable of reducing emission of radioactive substances, high in safety, high in concentration of recycled ammonia water and broad in application prospect.

Description

technical field [0001] The invention relates to a method for treating waste liquid, in particular to a method for recovering ammonia nitrogen in low-radioactive high-ammonia nitrogen waste liquid. Background technique [0002] High temperature gas-cooled reactor nuclear fuel element ceramic UO 2 The production of core particles adopts the sol-gel method. The gelling medium used is mainly ammonia water. The process includes two parts: wet method and dry method. The wet method includes steps such as dissolving, gelling, dispersing, aging, washing, and drying. . First, dissolve U by heating with analytically pure nitric acid 3 o 8 Prepare uranyl nitrate aqueous solution from solid powder, and formulate a colloid with a certain uranium concentration with various additives according to a certain formula and process, including urea, a binder, polyvinyl alcohol, and a cross-linking agent Organic matter such as tetrahydrofurfuryl alcohol; then, the glue is dispersed into uniform...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C02F1/04C01C1/02C02F101/16
Inventor 权英陈晓彤王阳刘兵唐亚平
Owner TSINGHUA UNIV
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