System for reducing concentration of gas-borne tritium in nuclear power plant building

A nuclear power plant and tritium concentration technology, applied in the field of radiation protection, can solve problems such as the inability to reduce the airborne tritium concentration of nuclear power plant buildings, the inability of dehumidifiers to function in tritium-containing exhaust gas, and the reduction of indoor air humidity, so as to reduce occupational exposure. , Improve the rate of tritium removal, the effect of simple maintenance

Inactive Publication Date: 2018-05-18
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

[0008] 1) Conventional dehumidifiers are mainly used to reduce the humidity of indoor air, inhale humid air in the room, and the "regenerated gas" after dehumidification will generally return to the room, and the "regenerated gas" after such treatment still contains tritium, so it cannot reduce the humidity. Effect of Airborne Tritium Concentration in Nuclear Power Plant Building
[0009] 2) When the dehumidifier of the conventional dehumidifier is regenerated, the evaporated moisture is finally discharged to the external environment, but because the dehumidification wastewater in the nuclear power plant building is radioactive wastewater, it cannot be directly discharged to the external environment
[0010] 3) There are many kinds of tritium-containing exhaust gases in nuclear power plant buildings, and conventional dehumidifiers cannot work on all tritium-containing exhaust gases

Method used

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  • System for reducing concentration of gas-borne tritium in nuclear power plant building

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Embodiment Construction

[0032] The present invention will be further described below in conjunction with the accompanying drawings and embodiments.

[0033] The invention provides a system for reducing airborne tritium concentration in a nuclear power plant building, which is used to remove the gas to be treated in the ventilation system of the nuclear power plant building (the gas to be treated is the gas in the nuclear power plant building and the gas in the ventilation system of the nuclear power plant building) Tritiated water vapor in gas), including enclosure 1 (see figure 1 ), a tritium water dehumidification device, and a tritium water collection device, wherein the tritium water dehumidification device and the tritium water collection device are arranged in the cabinet 1. The gas to be treated in the ventilation system of the nuclear power plant building enters the cabinet 1, the tritium water dehumidification device converts the tritiated water vapor in the gas to be treated into tritium wa...

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Abstract

The invention belongs to the technical field of radiation protection, and specifically relates to a system for reducing the concentration of gas-borne tritium in a nuclear power plant building. The system is used for removing tritiated water vapor in to-be-treated gas which is gas in the nuclear power plant building and in a ventilation system in the nuclear power plant building. The system comprises a tritiated water dehumidifying device and a tritiated water collecting device which are arranged in a device box (1), wherein the to-be-treated gas in the ventilation system enters the device box(1); the tritiated water vapor in the to-be-treated gas is converted into tritiated water through the tritiated water dehumidifying device; the tritiated water is collected through the tritiated water collecting device; and the to-be-treated gas with the tritiated water vapor removed is used as regenerated gas and discharged out of the device box (1). The system provided by the invention has fewactive components, is simple in maintenance, facilitates reducing of occupational exposure of workers, can reduce the content of the tritiated water vapor in the environment of the nuclear power plantbuilding, and reduces the concentration of the gas-borne tritium in the nuclear power plant building.

Description

technical field [0001] The invention belongs to the technical field of radiation protection, in particular to a system for reducing the concentration of airborne tritium in a nuclear power plant building. Background technique [0002] tritium( 3 H / T) is a pure β-ray emitter with a half-life of 12.35 years, the maximum energy of β-ray emission is 18.6keV, and the average energy is 5.7keV. In the pressurized water reactor nuclear power plant, tritium can be produced through the three-fission of nuclear fuel, the activation of boron in the burnable poison rod, and the activation of boron, lithium and deuterium in the main coolant when they flow through the core, etc., can produce tritium. According to the 2000 report of the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), as of 1997, the total amount of tritium released into the atmosphere by all nuclear power plants and fuel reprocessing plants in the world was 2.96×10 17 Bq, Tritium emission...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/02
CPCG21F9/02
Inventor 王雅霄毛亚蔚米爱军王晓霞高桂玲
Owner CHINA NUCLEAR POWER ENG CO LTD
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