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Nuclear power station radioactive waste gas treatment method

A technology for waste gas treatment and radioactive gas, used in radioactive purification, nuclear engineering and other directions, can solve the problems of safety to be improved, leakage of radioactive components, high operating pressure, and achieve the effect of reducing hydrogen content, reducing radioactive concentration, and strong pertinence

Inactive Publication Date: 2020-09-25
中核环保产业有限公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The purpose of the present invention is to provide a method for treating radioactive waste gas from a nuclear power plant, so as to solve the problems that the traditional radioactive waste gas treatment method proposed in the above-mentioned background technology has high operating pressure, the possibility of leakage of radioactive components, and the problem that the safety needs to be improved

Method used

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  • Nuclear power station radioactive waste gas treatment method
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Examples

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Effect test

Embodiment 1

[0031] A method for treating radioactive waste gas from a nuclear power plant, comprising the following steps:

[0032] (1) Catalytic oxidation composite advanced treatment:

[0033] 1a) After the gas-vapor mixture from the degasser, pressure relief box and coolant leakage collection box of the chemical volume system is condensed and dehumidified by the cooler, the remaining non-condensable gas is dehumidified with 234Nm 3 / h circulating nitrogen dilution, so that the hydrogen content in the exhaust gas does not exceed 2.5%;

[0034] 1b) After the diluted hydrogen-containing waste gas enters the buffer tank, it is evenly mixed with the added oxygen;

[0035] 1c) The mixed gas enters the recombiner after being heated to 140°C by a heater;

[0036] 1d) When the exhaust gas passes through the recombiner, hydrogen and oxygen are recombined into water at 350°C under the catalysis of platinum oxide, so that the hydrogen content in the residual gas does not exceed 0.2%;

[0037] 1...

Embodiment 2

[0042] A method for treating radioactive waste gas from a nuclear power plant, comprising the following steps:

[0043] (1) Catalytic oxidation composite advanced treatment:

[0044] 1a) After the gas-vapor mixture from the degasser, pressure relief box and coolant leakage collection box of the chemical volume system is condensed and dehumidified by the cooler, the remaining non-condensable gas is dehumidified with 220Nm 3 / h circulating nitrogen dilution, so that the hydrogen content in the exhaust gas does not exceed 2.5%;

[0045] 1b) After the diluted hydrogen-containing waste gas enters the buffer tank, it is evenly mixed with the added oxygen;

[0046] 1c) The mixed gas enters the recombiner after being heated to 130°C by a heater;

[0047] 1d) When the exhaust gas passes through the recombiner, hydrogen and oxygen are recombined into water at 380°C under the catalysis of platinum oxide, so that the hydrogen content in the residual gas does not exceed 0.2%;

[0048]1e...

Embodiment 3

[0053] A method for treating radioactive waste gas from a nuclear power plant, comprising the following steps:

[0054] (1) Catalytic oxidation composite advanced treatment:

[0055] 1a) After the gas-vapor mixture from the degasser, pressure relief box and coolant leakage collection box of the chemical volume system is condensed and dehumidified by the cooler, the remaining non-condensable gas is dehumidified with 200Nm 3 / h circulating nitrogen dilution, so that the hydrogen content in the exhaust gas does not exceed 2.5%;

[0056] 1b) After the diluted hydrogen-containing waste gas enters the buffer tank, it is evenly mixed with the added oxygen;

[0057] 1c) The mixed gas enters the recombiner after being heated to 150°C by a heater;

[0058] 1d) When the exhaust gas passes through the recombiner, hydrogen and oxygen are recombined into water at 320°C under the catalysis of platinum oxide, so that the hydrogen content in the residual gas does not exceed 0.2%;

[0059] 1...

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Abstract

The invention discloses a nuclear power station radioactive waste gas treatment method in the technical field of waste gas treatment. The method comprises the following steps: condensing and dehumidifying radioactive hydrogen-containing waste gas by a cooler, then diluting the waste gas by circulating nitrogen; introducing the waste gas into a buffer tank, uniformly mixing the waste gas with addedoxygen, heating the mixed gas by a heater, introducing the mixed gas into a recombiner, compounding hydrogen and oxygen into water at 300-400 DEG C under the catalytic action of platinum oxide, dehumidifying the residual gas by a cooler, and introducing part of the gas into an activated carbon retention bed for a purification treatment; dehumidifying residual gas by a dehumidifier, drying by a zeolite dryer, and then introducing the residual gas into the activated carbon retention bed for a purification treatment. The method can effectively reduce the hydrogen content in the radioactive hydrogen-containing waste gas, avoids explosion of the hydrogen-containing waste gas, adsorbs the radioactive hydrogen-containing waste gas through the activated carbon retention bed, reduces the radioactive concentration of the waste gas, and is high in pertinence, good in treatment effect, high in safety and suitable for nuclear power station waste gas treatment and radiation protection.

Description

technical field [0001] The invention relates to the technical field of waste gas treatment, in particular to a method for treating radioactive waste gas of a nuclear power plant. Background technique [0002] During normal operation and maintenance of nuclear power plants, nuclear power plants produce radioactive exhaust gases. According to the source and composition of waste gas, radioactive waste gas from nuclear power plants can be divided into two categories: oxygen-containing waste gas and hydrogen-containing waste gas. Among them, the oxygen-containing waste gas comes from the exhaust of various radioactive liquid temporary storage tanks, mainly containing oxygen, nitrogen, a small amount of iodine and aerosol particles. The radioactive level of this part of the waste gas is relatively low, and it is generally passed through the ventilation system of the auxiliary plant of the nuclear island. It can be discharged after treatment; while the hydrogen-containing waste ga...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/02
CPCG21F9/02
Inventor 杨均勇李明阳张冰赵子元
Owner 中核环保产业有限公司
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