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CN110444309B - Nuclear facility radioactive process waste gas treatment system - Google Patents

Nuclear facility radioactive process waste gas treatment system Download PDF

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Publication number
CN110444309B
CN110444309B CN201810083560.6A CN201810083560A CN110444309B CN 110444309 B CN110444309 B CN 110444309B CN 201810083560 A CN201810083560 A CN 201810083560A CN 110444309 B CN110444309 B CN 110444309B
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bed
detention
pipe
drying
inlet pipe
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CN110444309A (en
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李永国
史英霞
侯建荣
乔太飞
王瑞云
张继荣
俞杰
张渊
陈建利
吴波
霍明
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China Institute for Radiation Protection
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China Institute for Radiation Protection
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/02Treating gases

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  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Drying Of Gases (AREA)

Abstract

The invention relates to a nuclear facility radioactive process waste gas treatment system, which comprises an upstream gas source primary drying system, a drying bed group and a detention bed group, wherein the drying bed group comprises one or more drying beds, the detention bed group comprises one or more detention beds, and adjacent detention beds are connected through detention bed series pipes; the two ends of the drying bed are respectively provided with a drying bed air inlet pipe and a drying bed air outlet pipe, and the drying bed air inlet pipe is connected with an upstream air source primary drying system; the two ends of the detention bed are respectively connected with a detention bed air inlet pipe and a detention bed air outlet pipe, and the drying bed air outlet pipe is connected with the detention bed air inlet pipe; the air outlet pipe of the detention bed is connected with the air outlet main pipe of the detention bed, and the air outlet main pipe of the detention bed is connected with a chimney and a filter; the air outlet pipe of the dry bed is connected with the regeneration air supply system of the dry bed, and the air outlet pipe of the detention bed is connected with the regeneration air supply system of the detention bed. Provides better operation guarantee for the active carbon retention decay unit.

Description

Nuclear facility radioactive process waste gas treatment system
Technical Field
The invention belongs to the technical field of nuclear industry, and relates to a nuclear facility radioactive process waste gas treatment system.
Background
Nuclear plant radioactive process off-gas contains Xe, kr fission products, which typically need to be treated before it can be vented to the environment. Currently, the radioactive waste gas is mainly treated by two modes, namely pressurized storage decay and active carbon retention decay. The pressurized storage decay process mainly collects and sends the radioactive waste gas such as covering gas, purge exhaust gas, overhaul exhaust gas and the like stored in a container of a loop coolant into a buffer tank, after the buffer tank reaches a certain pressure, a downstream compressor is automatically started in a linkage mode, the waste gas is pressurized and conveyed into a decay tank for storage, and the radioactive level of short-life nuclides such as Xe, kr and the like is reduced through storage decay.
The active carbon detention decay process mainly comprises the steps that waste gas is condensed and dehumidified through a cooler to achieve the effect of pre-drying gas, the waste gas enters an active carbon protection bed, moisture in the waste gas is further removed, finally the waste gas enters the active carbon detention bed, short-life nuclides such as Xe, kr and the like in the waste gas are absorbed and detention, and the radioactivity level of the waste gas is reduced through decay. After the radioactivity is monitored to reach the standard, the waste gas is discharged to the environment through a ventilation system of the power plant. The active carbon detention decay process is superior to the pressurized storage decay process in system safety, operation convenience, space saving and other analysis.
The activated carbon material is sensitive to humidity, the adsorption performance of the activated carbon is reduced or even fails after the activated carbon is wetted, and the waste gas treatment system and an upstream system can be stopped, so that the waste gas humidity control is a key factor affecting the service life of the activated carbon and the usability of the system. The active carbon retention decay technology used at present does not contain a protection bed or adopts a single-row protection bed, and if front-end condensation dehumidification or the protection bed fails, the risk of unavailable active carbon failure exists. Meanwhile, the retention units used in China are not designed with the back-flushing regeneration function after the activated carbon adsorbs water.
Disclosure of Invention
The invention aims to solve the defects in the prior art and provides a nuclear facility radioactive process waste gas treatment system.
In order to achieve the above purpose, the technical scheme adopted by the invention is as follows:
the utility model provides a nuclear facility radioactive process exhaust gas treatment system, includes the preliminary drying system of upstream air supply, dry bed group, detention bed group, and dry bed group includes one or more dry beds, detention bed group includes one or more detention beds, connects through detention bed series connection pipe between the adjacent detention beds;
the two ends of the drying bed are respectively provided with a drying bed air inlet pipe and a drying bed air outlet pipe, and the drying bed air inlet pipe is connected with an upstream air source primary drying system;
the two ends of the detention bed are respectively connected with a detention bed air inlet pipe and a detention bed air outlet pipe, and the drying bed air outlet pipe is connected with the detention bed air inlet pipe;
the air outlet pipe of the detention bed is connected with the air outlet main pipe of the detention bed, and the air outlet main pipe of the detention bed is connected with a chimney and a filter;
the air outlet pipe of the dry bed is connected with the regeneration air supply system of the dry bed, and the air outlet pipe of the detention bed is connected with the regeneration air supply system of the detention bed.
The drying bed regeneration air supply system comprises a drying bed regeneration air supply pipe connected with an air outlet pipe of the drying bed, a drying nitrogen source interface connected with the drying bed regeneration air supply pipe, an electric heating unit arranged on the drying bed regeneration air supply pipe, and a port of the drying bed far away from the drying bed regeneration air supply pipe connected with a drying agent regeneration air exhaust pipeline.
In the above-mentioned nuclear facility radioactive process exhaust gas treatment system, the connection end of the drying agent regeneration gas exhaust pipeline is close to the drying bed air inlet pipe.
The nuclear facility radioactive process waste gas treatment system comprises a detention bed regeneration gas supply pipe connected with a detention bed gas outlet pipe, an emergency dry nitrogen source interface connected with the detention bed regeneration gas supply pipe, a detention bed gas inlet pipe connected with a detention bed blowback tail gas discharge pipe, and the detention bed blowback tail gas discharge pipe connected with a desiccant regeneration gas exhaust pipeline.
The primary drying system of the upstream air source comprises an air inlet pipe connected with an air inlet pipe of a drying bed, and an air cooler and an air-water separator are arranged on the air inlet pipe.
The nuclear facility radioactive process waste gas treatment system is characterized in that the gas-water separator is provided with a gas outlet and a water outlet, the gas outlet is connected with a drying bed gas inlet pipe, and the water outlet is connected with a collection point for containing liquid through a drain pipe.
In the above-mentioned nuclear facility radioactive process waste gas treatment system, the branch pipe of the air inlet pipe is connected with a nitrogen source interface.
According to the nuclear facility radioactive process waste gas treatment system, the branch pipeline of the air inlet pipe of the detention bed is connected with the active carbon purging tail gas outlet, and the air inlet pipe is provided with the active carbon purging tail gas inlet.
According to the nuclear facility radioactive process waste gas treatment system, the air inlet pipe is provided with the performance test injection port, and the detention bed air outlet main pipe and the detention bed serial pipe are provided with the downstream sampling port.
According to the nuclear facility radioactive process waste gas treatment system, the detention bed is connected with the pipe in series, the drying bed air inlet pipe, the drying bed air outlet pipe, the detention bed air inlet pipe, the detention bed air outlet main pipe, the drying bed regenerated air supply pipe, the detention bed back-blowing tail gas discharge pipe, and the air inlet pipe and the drain pipe are all provided with flow regulating valves.
The beneficial effects of the invention are as follows: the system comprises double-row protection beds, namely one for each. Meanwhile, a back blowing function and an active carbon performance field test interface are added after the active carbon absorbs moisture. The functional design provides better operation guarantee for the active carbon retention decay unit.
Drawings
Fig. 1 is a schematic diagram of the present invention.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
Example 1:
as shown in FIG. 1, a nuclear facility radioactive process exhaust gas treatment system comprises an upstream gas source primary drying system, a drying bed group and a detention bed group, wherein the drying bed group comprises one or more drying beds, the detention bed group comprises one or more detention beds, the drying bed group provided by the patent schematic diagram is provided with two parallel drying beds, namely a drying bed D1 and a drying bed D2, and the drying bed D1 and the drying bed D2 are connected in parallel.
The detention bed group provided in the schematic diagram of the patent is provided with three detention beds, namely detention bed E1, detention bed E2 and detention bed E3, activated carbon is filled in the detention beds, and the three detention beds are connected through a detention bed serial pipe 1;
the two ends of the drying bed D1 and the drying bed D2 are respectively provided with a drying bed air inlet pipe 2 and a drying bed air outlet pipe 3, and the drying bed air inlet pipe 2 is connected with an upstream air source primary drying system;
the two ends of the three detention beds are respectively connected with a detention bed air inlet pipe 4 and a detention bed air outlet pipe 5, and a drying bed air outlet pipe 3 is connected with the detention bed air inlet pipe 4;
the air outlet pipe 5 of the detention bed is connected with the air outlet main pipe 6 of the detention bed, and the air outlet main pipe 6 of the detention bed is connected with a chimney 7 and a filter 8;
further, the air outlet pipe 3 of the dry bed is connected with a regeneration air supply system of the dry bed, and the air outlet pipe 5 of the detention bed is connected with the regeneration air supply system of the detention bed.
The dry bed regeneration air supply system comprises a dry bed regeneration air supply pipe 9 connected with a dry bed air outlet pipe 3, a dry nitrogen source interface A7 connected with the dry bed regeneration air supply pipe 9, an electric heating unit 10 is arranged on the dry bed regeneration air supply pipe 9, the electric heating unit 10 is an electric heater RS001, a port, far away from the dry bed regeneration air supply pipe 9, of the dry bed is connected with a drying agent regeneration air exhaust pipeline 11, and the connecting end of the drying agent regeneration air exhaust pipeline 11 is close to the dry bed air inlet pipe 2.
The detention bed regeneration air supply system comprises a detention bed regeneration air supply pipe 12 connected with a detention bed air outlet pipe 5, an emergency dry nitrogen source interface A8 connected with the detention bed regeneration air supply pipe 12, a detention bed air inlet pipe 4 connected with a detention bed back-blowing tail gas discharge pipe 13, and the detention bed back-blowing tail gas discharge pipe 13 connected with a desiccant regeneration gas exhaust pipeline 11.
Further, the primary drying system of the upstream air source comprises an air inlet pipe 14 connected with the air inlet pipe 2 of the drying bed, an air cooler 15 and an air-water separator 16 are arranged on the air inlet pipe 14, the air-water separator 16 is provided with an air outlet and a water outlet, the air outlet is connected with the air inlet pipe 2 of the drying bed, the water outlet is connected with a collecting point 18 for containing liquid through a water outlet pipe 17, and a branch pipe of the air inlet pipe 14 is connected with a nitrogen source interface A1.
The branch pipeline of the air inlet pipe 4 of the detention bed is connected with an active carbon purging tail gas outlet, the active carbon purging tail gas outlet on the detention bed E1 is B2, the active carbon purging tail gas outlet on the detention bed E2 is B3, the active carbon purging tail gas outlet on the detention bed E3 is B4, the B2, the B3 or the B4 can also be used as an upstream sampling port, and the air inlet pipe 14 is provided with an active carbon purging tail gas inlet B1.
The air inlet pipe is provided with a performance test injection port A2 and A3, and the air outlet main pipe of the detention bed and the series pipe of the detention bed are provided with a downstream sampling port A6 and a downstream sampling port A4 or A5.
In order to conveniently control the flow and opening and closing of each pipeline, a detention bed serial pipe 1, a drying bed air inlet pipe 2, a drying bed air outlet pipe 3, a detention bed air inlet pipe 4, a detention bed air outlet pipe 5, a detention bed air outlet header pipe 6, a drying bed regeneration air supply pipe 9, a drying agent regeneration air exhaust pipe 11, a detention bed regeneration air supply pipe 12, a detention bed back blowing air exhaust pipe 13, an air inlet pipe 14 and a water outlet pipe 17 are all provided with flow regulating valves, wherein the air inlet pipe 14 is provided with flow regulating valves V001, V002, V003, the water outlet pipe 17 is provided with V004, the drying bed air inlet pipe 2 of the drying bed D1 is provided with V005, the drying bed air outlet pipe 3 is provided with V007, the drying bed air inlet pipe 2 of the drying bed D2 is provided with V006, the drying bed air outlet pipe 3 is provided with V008, the drying agent regeneration air exhaust pipe 11 is provided with V009, V010, the detention bed back blowing air exhaust pipe 13 is provided with V011, V012, the detention bed air detention bed E1 detention bed air inlet pipe 4 and the detention bed air outlet pipe 5 are respectively connected with V014 and V014, the detention bed air inlet pipe 4 and the detention bed air outlet pipe 5 are respectively connected with V017 and V024, the detention bed air inlet pipe 5 are respectively, the detention bed air inlet pipe is connected with V3 and the detention bed air inlet pipe is connected with V3, the position is connected with V024, the specific position is connected with V3, and the specific position is connected with the air inlet valve, and the air inlet valve is connected with the three-through V3.
The system can form a plurality of working conditions according to different communication modes of each pipeline, and is specifically as follows:
normal operation retention decay mode
The upstream exhaust gas passes through a gas cooler 15, a gas-water separator 16, a single row of drying beds, a single row or a plurality of rows of detention beds of activated carbon connected in series, and is discharged to a chimney 7 through a filter 8 after detention and decay. The valves which need to be opened in different operation processes are as follows:
(1) When using an E1 retention bed, the valve that needs to be opened is: v001, V002, V003, V005 (V005 closed when using D2, V006 open), V007 (V007 closed when using D2, V008 open), V011, V013, V014, V016, V019, V026, V020;
(2) When the E2 detention bed is used, V001, V002, V003, V005 (V005 is closed when D2 is used and V006 is opened), V007 (V007 is closed when D2 is used and V008 is opened), V011, V015, V016, V017, V018, V026 and V020;
(3) When the E3 retention bed is used, V001, V002, V003, V005 (V005 is closed when D2 is used and V006 is opened), V007 (V007 is closed when D2 is used and V008 is opened), V011, V019, V018, V025 and V020;
(4) When E1 and E2 are used for detention beds, V001, V002, V003, V005 (V005 is closed when D2 is used, V006 is opened), V007 (V007 is closed when D2 is used, V008 is opened), V013, V014, V017, V018, V026 and V020;
(5) When E1 and E3 are used for detention beds, V001, V002, V003, V005 (V005 is closed when D2 is used, V006 is opened), V007 (V007 is closed when D2 is used, V008 is opened), V013, V014, V016, V019, V018, V025 and V020;
(6) When E2 and E3 retention beds are used, V001, V002, V003, V005 (V005 is closed when D2 is used and V006 is opened), V007 (V007 is closed when D2 is used and V008 is opened), V015, V016, V017, V025, V026 and V020;
(7) When E1, E2, and E3 are used as the retention beds, V001, V002, V003, V005 (V005 is closed when D2 is used, V006 is open), V007 (V007 is closed when D2 is used, V008 is open), V013, V014, V017, V025, and V020.
(II) regeneration condition of drying bed
When the dry bed is regenerated, dry nitrogen is introduced from an A7 port, heated by an electric heater RS001, and heated, valves V007 and V009 are opened (when the D2 is regenerated, the valves V008 and V010 are opened). The exhaust gas enters the ventilation duct through the desiccant regeneration gas exhaust line 11.
(III) active carbon water absorption emergency back blowing working condition
When the water content exceeds the designed value due to the adsorption of the water by the detention bed of the activated carbon, the system is started to dry the nitrogen and blow back the activated carbon for regeneration. Dry nitrogen enters from the A8 port, and is opened by V022 (or V023 or V024), V018 (or V016 or V013), V019 (closed when E1 and E2 are back-blown), V015 (closed when E1 is back-blown) and V012 (opened when the radioactivity concentration of back-blown tail gas is lower than the emission requirement).
When the activity concentration of the back-blowing tail gas is higher than the emission requirement, V012 is closed, B1 is connected through B2, B3 or B4, and the back-blowing tail gas is dried by a drying bed and then is discharged to the chimney 7 through retention decay of an active carbon retention bed without back-blowing.
(IV) operation conditions of the retention bed Performance test
After the detention unit of the radioactive waste gas treatment system is debugged for the first time or operated for a certain period, the performance of the detention bed needs to be subjected to field test. During the test, the air source enters from the front end of the upstream gas cooler or the port A1, the tracer is injected from the port A2 (or the port A3), the upstream sampling port B2 or the port B3 or the port B4, and the downstream sampling port A4 or the port A5 or the port A6.
The functional design provides better operation guarantee for the active carbon retention decay unit.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.

Claims (9)

1. The nuclear facility radioactive process waste gas treatment system comprises an upstream gas source primary drying system, a drying bed group and a detention bed group, and is characterized in that the drying bed group comprises more than one drying bed, the detention bed group comprises more than two detention beds, and adjacent detention beds are connected through detention bed series pipes;
the two ends of the drying bed are respectively provided with a drying bed air inlet pipe and a drying bed air outlet pipe, and the drying bed air inlet pipe is connected with an upstream air source primary drying system;
the two ends of the more than two detention beds are respectively connected with a detention bed air inlet pipe and a detention bed air outlet pipe, and the drying bed air outlet pipe is connected with the detention bed air inlet pipe;
the air outlet pipe of the detention bed is connected with the air outlet main pipe of the detention bed, and the air outlet main pipe of the detention bed is connected with a chimney and a filter;
the air outlet pipe of the drying bed is connected with the regeneration air supply system of the drying bed, the air outlet pipe of the detention bed is connected with the regeneration air supply system of the detention bed,
the detention bed regeneration air supply system comprises a detention bed regeneration air supply pipe connected with a detention bed air outlet pipe, an emergency dry nitrogen source interface connected with the detention bed regeneration air supply pipe, a detention bed air inlet pipe connected with a detention bed back-blowing tail gas discharge pipe, and the detention bed back-blowing tail gas discharge pipe connected with a desiccant regeneration gas exhaust pipeline;
the branch pipeline of the air inlet pipe of the detention bed is connected with the active carbon purging tail gas outlet, the active carbon purging tail gas outlet on the detention bed is used as an upstream sampling port, the air inlet pipe is provided with the active carbon purging tail gas inlet, when the activity concentration of the back-blowing tail gas is higher than the emission requirement, the active carbon purging tail gas inlet is controlled by the control valve and connected with the branch pipeline of the air inlet pipe of the detention bed, and the back-blowing tail gas is dried by the drying bed and then is detention and decayed by the detention bed of the active carbon without back-blowing and discharged to a chimney.
2. The nuclear facility radioactive process exhaust gas treatment system according to claim 1, wherein the dry bed regeneration gas supply system comprises a dry bed regeneration gas supply pipe connected with a dry bed gas outlet pipe, a dry nitrogen source interface connected with the dry bed regeneration gas supply pipe, an electric heating unit arranged on the dry bed regeneration gas supply pipe, and a port of the dry bed far from the dry bed regeneration gas supply pipe connected with a drying agent regeneration gas exhaust pipeline.
3. A nuclear plant radioactive process exhaust treatment system according to claim 2, wherein the connection end of the desiccant regeneration gas exhaust line is adjacent to the desiccant bed inlet pipe.
4. The nuclear facility radioactive process exhaust gas treatment system of claim 1, wherein the upstream gas source primary drying system comprises a gas inlet pipe connected with a dry bed gas inlet pipe, and a gas cooler and a gas-water separator are arranged on the gas inlet pipe.
5. The nuclear plant radioactive process exhaust gas treatment system of claim 4, wherein the gas-water separator has an air outlet and a water outlet, the air outlet is connected to the dry bed air inlet pipe, and the water outlet is connected to the collection point for receiving the liquid through the water outlet pipe.
6. The nuclear facility radioactive process exhaust gas treatment system of claim 4, wherein the branched pipe of the gas inlet pipe is connected to a nitrogen source interface.
7. The nuclear facility radioactive process exhaust gas treatment system according to claim 4, wherein the branched pipeline of the air inlet pipe of the detention bed is connected with an activated carbon purging exhaust gas outlet, and the air inlet pipe is provided with an activated carbon purging exhaust gas inlet.
8. The nuclear plant radioactive process exhaust gas treatment system of claim 4, wherein the inlet pipe is provided with a performance test injection port, and the detention bed outlet main pipe and the detention bed serial pipe are provided with downstream sampling ports.
9. The nuclear facility radioactive process exhaust gas treatment system according to claim 5, wherein the detention bed serial pipe, the drying bed air inlet pipe, the drying bed air outlet pipe, the detention bed air inlet pipe, the detention bed air outlet main pipe, the drying bed regenerated air supply pipe, the detention bed back-blowing exhaust gas discharge pipe, the air inlet pipe and the water outlet pipe are provided with flow regulating valves.
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Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112717625A (en) * 2020-11-23 2021-04-30 岭东核电有限公司 Hydrogen-containing waste gas treatment system of nuclear power station
CN112755987B (en) * 2020-12-29 2024-07-16 江苏核电有限公司 Device for on-line vacuum drying and regenerating of activated carbon of retention bed of nuclear power unit
CN113963829A (en) * 2021-10-27 2022-01-21 中国核动力研究设计院 Method and system for treating radioactive waste gas of isotope production line
CN114883022B (en) * 2022-05-12 2023-06-27 华能核能技术研究院有限公司 High-temperature reactor purification and regeneration waste gas treatment system and method
CN115193216B (en) * 2022-07-15 2023-08-25 江苏希捷新能源工程技术有限公司 Nuclear power station waste gas treatment system based on activated carbon delay bed and application method thereof

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE668204A (en) * 1964-08-14 1965-12-01
JPH06347593A (en) * 1993-06-11 1994-12-22 Toshiba Corp Treatment for radioactive waste gas
JPH0961589A (en) * 1995-08-21 1997-03-07 Toshiba Corp Dehumidifying device for radioactive gas waste processing device
JPH09281290A (en) * 1996-04-11 1997-10-31 Toshiba Corp Radioactive gaseous waste treating device
CN104157318A (en) * 2014-08-12 2014-11-19 中广核工程有限公司 Treatment system for hydrogen-containing radioactive waste gas in nuclear power station
CN204045226U (en) * 2014-09-05 2014-12-24 武汉海王新能源工程技术有限公司 A kind of dry ice decontamination plant for removing radiation
CN105355249A (en) * 2015-11-16 2016-02-24 中广核工程有限公司 Radioactive waste gas processing device for nuclear power station
CN105572299A (en) * 2014-10-13 2016-05-11 中国辐射防护研究院 Testing system for performance of drying agent of dehumidifying and drying unit of gaseous radioactive waste processing system

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101847456A (en) * 2009-06-24 2010-09-29 中广核工程有限公司 Waste gas treatment method of nuclear power plant and treatment device thereof
CN103474121B (en) * 2013-09-24 2016-09-14 中广核工程有限公司 Nuclear power station Spent Radioactive gas processing system
CN104143368B (en) * 2014-08-12 2017-01-25 中广核工程有限公司 Nuclear power station radioactive waste gas treatment system
CN105572298B (en) * 2014-10-13 2019-07-02 中国辐射防护研究院 Radioactive emission processing unit inert gas is detained bed Properties of Activated Carbon pilot system
CN106563412A (en) * 2015-10-09 2017-04-19 江苏核电有限公司 Regeneration method used for activated carbon of delay bed of nuclear power station

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE668204A (en) * 1964-08-14 1965-12-01
JPH06347593A (en) * 1993-06-11 1994-12-22 Toshiba Corp Treatment for radioactive waste gas
JPH0961589A (en) * 1995-08-21 1997-03-07 Toshiba Corp Dehumidifying device for radioactive gas waste processing device
JPH09281290A (en) * 1996-04-11 1997-10-31 Toshiba Corp Radioactive gaseous waste treating device
CN104157318A (en) * 2014-08-12 2014-11-19 中广核工程有限公司 Treatment system for hydrogen-containing radioactive waste gas in nuclear power station
CN204045226U (en) * 2014-09-05 2014-12-24 武汉海王新能源工程技术有限公司 A kind of dry ice decontamination plant for removing radiation
CN105572299A (en) * 2014-10-13 2016-05-11 中国辐射防护研究院 Testing system for performance of drying agent of dehumidifying and drying unit of gaseous radioactive waste processing system
CN105355249A (en) * 2015-11-16 2016-02-24 中广核工程有限公司 Radioactive waste gas processing device for nuclear power station

Non-Patent Citations (5)

* Cited by examiner, † Cited by third party
Title
AP1000核电站放射性气体废物系统的改进研究;刘骞;《工业设计》;全文 *
Management of radioactive waste gasses from PET radiopharmaceutical synthesis using cost effective capture systems integrated with a cyclotron safety system;stimison,DHR et al.;《Journal of Radiology Protection》;全文 *
Management of radioactive wastes;Wm. L. Lennemann et al.;《Annals of Nuclear Energy》;全文 *
用于快堆电站放射性气体处理的工艺研究;和丹 等;《中国核科学技术进展报告(第四卷)——中国核学会2015年学术年会论文集第10册(核安全分卷)》;全文 *
用于核电站放射性惰性气体处理的常温活性炭滞留床研究;郭亮天 等;《辐射防护》;19940131;全文 *

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