CN109712738A - The Spent Radioactive gas processing system of marine floating nuclear power platform - Google Patents

The Spent Radioactive gas processing system of marine floating nuclear power platform Download PDF

Info

Publication number
CN109712738A
CN109712738A CN201910098642.2A CN201910098642A CN109712738A CN 109712738 A CN109712738 A CN 109712738A CN 201910098642 A CN201910098642 A CN 201910098642A CN 109712738 A CN109712738 A CN 109712738A
Authority
CN
China
Prior art keywords
delay tank
tank
delay
type compressor
diaphragm type
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201910098642.2A
Other languages
Chinese (zh)
Inventor
肖鑫
鲜春媚
周文琪
吴婉烨
廖聪
温恩龙
方震
贺梅葵
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
719th Research Institute of CSIC
Original Assignee
719th Research Institute of CSIC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 719th Research Institute of CSIC filed Critical 719th Research Institute of CSIC
Priority to CN201910098642.2A priority Critical patent/CN109712738A/en
Publication of CN109712738A publication Critical patent/CN109712738A/en
Pending legal-status Critical Current

Links

Landscapes

  • Measurement Of Radiation (AREA)

Abstract

The invention discloses a kind of Spent Radioactive gas processing systems of marine floating nuclear power platform, including surge tank, diaphragm type compressor, cooler, moisture trap, delay tank, iodine adsorption cleaning unit, blower and chimney, the entrance of surge tank is connected with the hydrogeneous exhaust pipe of up-stream system, outlet is connected with the air inlet of diaphragm type compressor, the exhaust pipe and cooler of diaphragm type compressor, moisture trap is sequentially connected in series, diaphragm type compressor, the both ends of the cooling water pipe of cooler respectively with the input of component cooling water system, efferent duct is connected, the exhaust outlet of moisture trap is connected with delay tank air inlet, the exhaust pipe of delay tank is connected with iodine adsorption cleaning unit, the rear end of iodine adsorption cleaning unit is sequentially connected in series blower, flowmeter, finally lead to chimney, carry out high point discharge.The present invention sufficiently decays to the hydrogeneous exhaust gas generated on floating nuclear power plant using pressurization banking system, ensure that inert gas in exhaust gas, iodine, aerosol and particle are removed to the greatest extent.

Description

The Spent Radioactive gas processing system of marine floating nuclear power platform
Technical field
The present invention relates to marine floating nuclear power platform technology fields, in particular to a kind of radiation of marine floating nuclear power platform Property exhaust treatment system.
Background technique
The processing of nuclear power station radioactive emission refer to radioactive emission is controlledly drained into power station atmosphere outside it Before, therefrom separate or remove the process of radioactive component and chemical pollutant.Currently, the treatment process of hydrogeneous exhaust gas is broadly divided into Two kinds of storage method of active carbon adsorption and pressurization.
Active carbon adsorption is to be adsorbed using loose porous active carbon to radioactivity inert gas, fission gas (Xe, Kr etc.) is postponed by active carbon Dynamic Adsorption, through-rate relative hydrogen and nitrogen, is declined in timing period Become.However the retention characteristics of fission gas are related with temperature, pressure and flow, treatment effect is unstable.Active carbon be easy by Tide is unfavorable for using in the environment of high humidity with high salt.And the secondary waste production of the treatment process is big, is not suitable for sea floating core The hydrogeneous exhaust-gas treatment in power station.
Pressurization storage decay is that all kinds of airborne radioactivity waste collections are stored in pressure vessel using diaphragm type compressor It decays, the decay time (60d) for reaching certain is filtered processing again.The suitable marine hot and humid environment of the technique, two Secondary waste is few, however the hydrogeneous exhaust gas of land nuclear power station pressurization storage decay system space occupied is big, and trouble-saving and alleviation are arranged Apply deficiency.It cannot indiscriminately imitate and be applied on marine floating nuclear power platform.
Therefore, it is necessary to the characteristics of being directed to the hydrogeneous exhaust gas that marine floating nuclear power platform generates and marine environmental conditions, if A kind of hydrogeneous exhaust treatment system suitable for floating nuclear power plant is counted, guarantees that the discharge of Airborne Effluent meets environmental protection Accelerate to realize leap of the civilian nuclear energy from land to ocean it is required that being conducive to China.
Summary of the invention
It is an object of the invention to overcome the deficiencies in the prior art, propose a kind of Spent Radioactive of marine floating nuclear power platform Gas processing system is effectively treated the hydrogeneous exhaust gas generated on marine floating nuclear power platform, guarantees that treated gas is living Degree meets limit value requirement as defined in standard.
To achieve the above object, the Spent Radioactive gas processing system of the marine floating nuclear power platform designed by the present invention, It is characterized in that, including surge tank, diaphragm type compressor, cooler, moisture trap, delay tank, iodine adsorption cleaning unit, wind Machine and chimney, the entrance of the surge tank be connected with the hydrogeneous exhaust pipe of up-stream system, outlet and diaphragm type compressor into Port is connected, and exhaust pipe and cooler, the moisture trap of the diaphragm type compressor are sequentially connected in series, the diaphragm type compressor, cold But the both ends of the cooling water pipe of device are connected with the input of component cooling water system, efferent duct respectively, the row of the moisture trap Port is connected with delay tank air inlet, and the exhaust pipe of the delay tank is connected with iodine adsorption cleaning unit, the iodine adsorption cleaning The rear end of unit is sequentially connected in series blower, flowmeter, finally leads to chimney, carries out high point discharge.
Further, the diaphragm type compressor include the first diaphragm type compressor parallel with one another, mutual backup and second every Film compressor, exhaust pipe and the first cooler, the first moisture trap of first diaphragm type compressor are sequentially connected in series, and described The exhaust pipe of two diaphragm type compressors is sequentially connected in series with the second cooler, the second moisture trap.
Further, first diaphragm type compressor and the second diaphragm type compressor, the first cooler and the second cooler Cooling water pipe it is parallel with one another, water inlet is connected with component cooling water system water inlet pipe, water outlet and component cooling water system Return pipe is connected, and cooling by component cooling water system progress central water supply, the rear end of water inlet pipe and return pipe sets cooling water respectively Inflow temperature sensor and cooling water return water temperature sensor, are monitored for the temperature to component cooling water.
Further, the delay tank includes the first delay tank, the second delay tank and third delay tank of mutual backup, The exhaust outlet of the moisture trap is connected with the first delay tank, the second delay tank and third delay tank, the first delay tank, It is respectively equipped with pressure sensor, temperature sensor and liquid level sensor on two delay tanks and third delay tank, respectively to pressure, temperature Degree, liquid level are monitored, and the exhaust pipe of first delay tank, the second delay tank and third delay tank is in parallel, by delay tank It is vented electric diaphragm valve and iodine adsorption cleaning unit circulates.
Further, the iodine adsorption cleaning unit includes electric heater, prefilter, high efficiency particulate air filter, iodine absorption Device and postposition high efficiency particulate air filter, for electric heater for exhaust gas to be dried, prefilter and high efficiency particulate air filter are useless for removing Particle and aerosol in gas, iodine adsorber are used for the methyl iodide and elemental iodine gone in removing exhaust gas, and postposition high efficiency particulate air filter is used for Retain the active carbon particle that air-flow carries.
It further, further include nitrogen sparge tube road, the air inlet and nitrogen source capsule on the nitrogen sparge tube road pass through After nitrogen pipeline electric diaphragm valve and the first pressure reducing valve, with surge tank, diaphragm type compressor, cooler, moisture trap and decay The air inlet pipe of case is connected.
It further, further include sampling line, on first delay tank, the second delay tank and third delay tank respectively It is provided with the first sampling electric diaphragm valve, the second sampling electric diaphragm valve, third sampling electric diaphragm valve, sampling line merges into One the second pressure reducing valve of road leads to the sampling system reception pipe of nuclear power platform, is sampled analysis to ageing effect.
Further, oxygen content analyzer is provided on the surge tank.
Further, it is respectively arranged on first delay tank, the second delay tank and third delay tank and surge tank First delay tank liquid level sensor, the second delay tank liquid level sensor, third delay tank liquid level sensor, surge tank level sensing Device, the first delay tank liquid level sensor, the second delay tank liquid level sensor, third delay tank liquid level sensor, surge tank When the collection value of liquid level sensor reaches threshold value, it is respectively arranged at the first delay tank, the second delay tank, third delay tank and buffering Release water electric diaphragm valve, the second release water electric diaphragm valve, the third of the first of pot bottom is released water electric diaphragm valve and buffering Tank is released the unlatching of water electric diaphragm valve, and the liquid in the first delay tank, the second delay tank and third delay tank and surge tank is in weight Liquid Radwaste Treatment reception pipe is discharged under power effect.
Further, first delay tank, the second delay tank and third delay tank pass through respectively first fall case it is electronic Diaphragm valve, the second electric diaphragm valve of falling case are connected with the air inlet pipe of the first diaphragm type compressor and the second diaphragm type compressor.
The invention has the benefit that firstly, the present invention is based on conventional press storage decay techniques to improve, using adding Pressure banking system sufficiently decays to the hydrogeneous exhaust gas generated on floating nuclear power plant, molten to gas using multistage filtering mode Glue and iodine can sufficiently filter removal, ensure that inert gas in exhaust gas, iodine, aerosol and particle can be gone to the greatest extent It removes, meets the principle of " reasonable is low as far as possible " of nuclear power industry;Secondly, the present invention devises 2 diaphragm type compressors and 3 are declined Becoming case, it is ensured that the continuous operation of system in the case of single failure, each delay tank have two sets of mutually independent air inlet pipe, When it is leaked, the quickly operation of falling case can be carried out by spare diaphragm type compressor, to will not influence normal delay tank Intake operation ensure that down that case and pressurization can carry out simultaneously;Finally, the invention proposes all standings of internal system gas-phase space Theory carries out nitrogen purging to the gas-phase space in all containing boundaries of exhaust gas, ensure that internal system exhaust gas residual volume can Drop to level low as far as possible.
Detailed description of the invention
Fig. 1 is the overall structure diagram of the Spent Radioactive gas processing system of the marine floating nuclear power platform of the present invention.
Fig. 2 is enlarged diagram at a in Fig. 1.
Fig. 3 is enlarged diagram at b in Fig. 1.
Fig. 4 is enlarged diagram at c in Fig. 1.
Fig. 5 is enlarged diagram at d in Fig. 1.
In figure: surge tank 1, the first diaphragm type compressor 2, the second diaphragm type compressor 3, the first cooler 4, the second cooler 5, First moisture trap 6, the second moisture trap 7, the first delay tank 8, the second delay tank 9, third delay tank 10, iodine absorption are net Change unit 11, blower 12, chimney 13, surge tank export electric diaphragm valve 14, the first compressor electric diaphragm valve 15, first fall case Electric diaphragm valve 16, the second compressor electric diaphragm valve 17, the second electric diaphragm valve of falling case 18, the first delay tank exhaust it is electronic every Film valve 21, the first delay tank air inlet electric diaphragm valve 22, the 4th delay tank air inlet electric diaphragm valve 23, the first electronic diaphragm of sampling Valve 24, the second delay tank are vented electric diaphragm valve 25, and the second delay tank air inlet electric diaphragm valve 26, the 5th delay tank air inlet is electronic Diaphragm valve 27, second sampling electric diaphragm valve 28, third delay tank be vented electric diaphragm valve 29, third delay tank air inlet it is electronic every Film valve 30, the 6th delay tank air inlet electric diaphragm valve 31, third sample electric diaphragm valve 32, and delay tank is vented electric diaphragm valve 33, fan motor diaphragm valve 34, nitrogen pipeline electric diaphragm valve 35, surge tank releases water electric diaphragm valve 44, and first releases water Electric diaphragm valve 47, second releases water electric diaphragm valve 48, and third is released water electric diaphragm valve 49, surge tank outlet non-return valve 58, the first check valve 59, second one-way valve 60, the first pressure reducing valve 71, the second pressure reducing valve 72, oxygen content analyzer 73, cooling water into Water temperature sensor 74, cooling water return water temperature sensor 75, the first cooler inflow temperature sensor 76, the second cooler into Water temperature sensor 77, the first cooler leaving water temperature sensors 78, the second cooler leaving water temperature sensors 79, the first decay Case temperature sensor 80, the second delay tank temperature sensor 81, third delay tank temperature sensor 82, buffer tank pressure sensor 84, the first delay tank pressure sensor 85, the second delay tank pressure sensor 86, third delay tank pressure sensor 87, buffering Tank level indicator 88, the first delay tank liquid level sensor 89, the second delay tank liquid level sensor 90, third delay tank liquid level pass Sensor 91, flowmeter 92.
Specific embodiment
Below in conjunction with the drawings and specific embodiments, the present invention is described in further detail.
As shown in fig. 1~fig. 5, the Spent Radioactive gas processing system of marine floating nuclear power platform proposed by the present invention, including Surge tank 1, diaphragm type compressor, cooler, moisture trap, delay tank, iodine adsorption cleaning unit 11, blower 12 and chimney 13.
The entrance of surge tank 1 is connected with the hydrogeneous exhaust pipe A of up-stream system, for buffering the impact of upstream airflow, Make the diaphragm type compressor of rear end can be with even running.It is passed on surge tank 1 configured with buffer tank pressure sensor 84, surge tank liquid level Sensor 88 and oxygen content analyzer 73 are respectively monitored pressure, liquid level and the oxygen content in surge tank 1.The outlet of surge tank 1 Through surge tank outlet electric diaphragm valve 14, surge tank outlet non-return valve 58 and the first diaphragm type compressor 2, the second diaphragm type compressor 3 Air inlet be connected.
First diaphragm type compressor 2, the air entry of the second diaphragm type compressor 3 are parallel with one another, mutual backup.First membrane compresses It connects on machine 2 and the air inlet pipe of surge tank 1 first compressor electric diaphragm valve 15, the air inlet pipe of diaphragm type compressor 3 and surge tank 1 The second compressor electric diaphragm valve 17 of upper series connection.The exhaust pipe of diaphragm type compressor 2 has been sequentially connected in series the first cooler 4 and the first gas Separator 6, the exhaust pipe of diaphragm type compressor 3 has been sequentially connected in series the second cooler 5 and the second moisture trap 7, after compression Gas cooled down and dried.
First 4 pairs of cooler is cooled down through the compressed exhaust gas of the first diaphragm type compressor 2, water inlet pipe and outlet pipe point It is not provided with the first cooler inflow temperature sensor 76 and the first cooler leaving water temperature sensors 78.Second cooler 5 is right It is cooled down through the compressed exhaust gas of diaphragm type compressor 3, water inlet pipe and outlet pipe are respectively arranged with the second cooler water inlet temperature Spend sensor 77 and the second cooler leaving water temperature sensors 79.Temperature sensor is used to carry out the exhaust gas temperature of cooling front and back Monitoring.
The cooling water pipe phase of first diaphragm type compressor 2, the second diaphragm type compressor 3, the first cooler 4 and the second cooler 5 Mutually in parallel, water inlet is connected with component cooling water system water inlet pipe C1, the return pipe C2 phase of water outlet and component cooling water system Even.Central water supply cooling is carried out by component cooling water system, water inlet pipe C1 and the rear end return pipe C2 are respectively equipped with cooling water water inlet Temperature sensor 74 and cooling water return water temperature sensor 75, are monitored for the temperature to component cooling water.
The exhaust outlet of first moisture trap 6 is by pipeline through the first check valve 59 and the first delay tank 8, the second delay tank 9 and third delay tank 10 communicate, the intake valve of corresponding delay tank is respectively that the first delay tank air inlet electric diaphragm valve 22, second declines Become case air inlet electric diaphragm valve 26 and third delay tank air inlet electric diaphragm valve 30.First delay tank 8, the second delay tank 9 and Three delay tanks 10 are mutual standby.The exhaust outlet of second moisture trap 7 is by pipeline through second one-way valve 60 and decay Case 8, delay tank 9 and delay tank 10 communicate, the intake valve of corresponding delay tank be respectively the 4th delay tank air inlet electric diaphragm valve 23, 5th delay tank air inlet electric diaphragm valve 27 and the 6th delay tank air inlet electric diaphragm valve 31.It is respectively equipped on first delay tank 8 First delay tank pressure sensor 85, the first delay tank temperature sensor 80 and the first delay tank liquid level sensor 89, it is right respectively Pressure, temperature and liquid level are monitored.Second delay tank 9 is equipped with the second delay tank pressure sensor 86, second decay box temperature Sensor 81 and the second delay tank liquid level sensor 90 are spent, pressure, temperature and liquid level are monitored respectively.Third delay tank 10 It is equipped with third delay tank pressure sensor 87, third delay tank temperature sensor 82 and third delay tank liquid level sensor 91, Pressure, temperature and liquid level are monitored respectively.
The exhaust pipe of first delay tank 8, the second delay tank 9 and third delay tank 10 is in parallel, and gas exhausting valve is respectively the One delay tank is vented electric diaphragm valve 21, the second delay tank exhaust electric diaphragm valve 25 and third delay tank and is vented electric diaphragm valve 29.Delay tank exhaust can be vented electric diaphragm valve 33 through delay tank and lead to iodine adsorption cleaning unit 11, be filtered except after iodine etc. Continuous processing, power are provided by blower 12.First delay tank 8, the second delay tank 9 and third delay tank 10 can also by first fall case The air inlet with the first diaphragm type compressor 2 and the second diaphragm type compressor 3 respectively of electric diaphragm valve 16, the second electric diaphragm valve of falling case 18 Pipe is connected, and carries out the operation of falling case, the gas in the delay tank leaked will occurs and be injected into spare delay tank.
Iodine adsorption cleaning unit 11 includes electric heater, prefilter, high efficiency particulate air filter, iodine adsorber and the efficient mistake of postposition Exhaust gas is dried in filter, heater, the particle and aerosol that prefilter and high efficiency particulate air filter are used to go in removing exhaust gas, iodine Absorber is used for the methyl iodide and elemental iodine gone in removing exhaust gas, and the active carbon that postposition high efficiency particulate air filter is used to retain air-flow carrying is broken Grain.The rear end of iodine adsorption cleaning unit 11 is sequentially connected in series blower 12, flowmeter 92, finally leads to chimney 13, carries out high point discharge.
This system further includes nitrogen sparge tube road, and surge tank 1, diaphragm type compressor, moisture trap, delay tank are by pressure empty set System provides source nitrogen the B covering and the purging that carry out headroom, and nitrogen source capsule B is depressurized through nitrogen pipeline electric diaphragm valve 35 and first After valve 71, respectively with surge tank 1, the first diaphragm type compressor 2 and the second diaphragm type compressor 3, the first moisture trap 6 and the second gas Separator 7, the first delay tank 8, the second delay tank 9 are connected with the air inlet pipe of third delay tank 10.
Surge tank 1, the first diaphragm type compressor 2 and the second diaphragm type compressor 3, the first moisture trap 6 and the second air water point After in parallel from the water pipe of releasing of device 7, the first delay tank 8, the second delay tank 9 and third delay tank 10 with radioactive liquid waste processing system The reception pipe D of system is communicated.When the first delay tank liquid level sensor 89, the second delay tank liquid level sensor 90, third delay tank liquid Level sensor 91, the collection value for buffering tank level indicator 88 be when reaching threshold value, is respectively arranged at the first delay tank 8, second declines Become case 9,1 bottom of third delay tank 10 and surge tank first release water electric diaphragm valve 47, second release water electric diaphragm valve 48, third releases water electric diaphragm valve 49 and surge tank is released the unlatching of water electric diaphragm valve 44, the decay of the first delay tank 8, second Liquid in case 9 and third delay tank 10 and surge tank 1 is discharged into Liquid Radwaste Treatment reception pipe D under the effect of gravity.
This system further includes sampling line, is respectively arranged with first on the first delay tank 8, delay tank 9 and delay tank 10 and takes Sample electric diaphragm valve 24, second samples electric diaphragm valve 28, third samples electric diaphragm valve 32, and sampling line merges into Yi Tiaolu The sampling system reception pipe E for leading to nuclear power platform through the second pressure reducing valve 72, is sampled analysis to ageing effect.
The workflow of the hydrogeneous exhaust treatment system of sea floating nuclear power platform of the invention are as follows:
Hydrogeneous exhaust gas source A from up-stream system enters in surge tank 1, and the impact of buffer gas flow guarantees the diaphragm of rear end Compressor can be with even running, and the oxygen content analyzer 73 being set on surge tank 1 detects that oxygen content reaches 2% in surge tank When, nitrogen pipeline electric diaphragm valve 35 is opened, nitrogen covering is carried out to headroom in surge tank by source nitrogen B the supply of nitrogen, is prevented Only hydrogen explosion closes the electronic diaphragm of nitrogen pipeline when oxygen content analyzer 73 detects that oxygen content drops to 0.1% in surge tank Valve 35.In surge tank 1 pressure reach open after setting value surge tank outlet electric diaphragm valve 14, surge tank outlet non-return valve 58 with First compressor electric diaphragm valve 15 enters the first diaphragm type compressor 2, and compressed gas carries out cold into the first cooler 4 But, the first cooler inflow temperature sensor 76 and the first cooler leaving water temperature sensors 78 can be to the gas temperatures of cooling front and back Degree is monitored, accordingly the flow of adjustment equipment cooling water inlet pipe C1, with guarantee gas temperature after cooling drop to 50 DEG C with Under.Gas after cooling enters the first moisture trap 6 and is dried, and the gas after drying declines through the first check valve 59 with first Become case 8, the second delay tank 9 and third delay tank 10 to communicate, the intake valve of corresponding delay tank is respectively the first delay tank air inlet electricity Dynamic diaphragm valve 22, the second delay tank air inlet electric diaphragm valve 26 and third delay tank air inlet electric diaphragm valve 30.According to delay tank On pressure sensor judge the state of delay tank, select cracking pressure to be shown as delay tank such as the first delay tank 8 of normal pressure Intake valve.Gas decays 60 days in the first delay tank 8, and wherein abundant decay can be obtained in the inert gases such as Kr, Xe, opens first Electric diaphragm valve 24 is sampled, gas, toward sampling system, is sampled analysis, such as meets activity through the second pressure reducing valve 72 decompression heel row Meet emission limit standard, then opens the first delay tank exhaust electric diaphragm valve 21, exhaust gas is vented electric diaphragm valve through delay tank 33, into iodine adsorption cleaning unit 11, power is provided by blower 12, and blower rear end is in series with fan motor diaphragm valve 34 and is arranged Switch control is put, flowmeter 92 carries out flow monitoring to the exhaust gas for draining into chimney 13.Processing of the gas through the second diaphragm type compressor 3 Process is similar with the first diaphragm type compressor 2, repeats no more.
After treatment opens nitrogen sparge tube road, to surge tank 1, the first diaphragm type compressor 2 and the second diaphragm type compressor 3, in the first moisture trap 6 and the second moisture trap 7, the first delay tank 8, the second delay tank 9 and third delay tank 10 The purging of headroom, remaining exhausted air quantity is preferably minimized in guarantee system, to reduce the radioactive dose of routine inspection staff.
First delay tank 8, the second delay tank 9 and third delay tank 10 are mutually spare relationship, the state of normal operation Always 1 receiving exhaust gas, 1 storing decay exhaust gas, the last one is in spare armed state.When wherein 1 fills When having the delay tank of exhaust gas such as the first delay tank 8 leaking, start spare diaphragm type compressor such as the second diaphragm type compressor 3, working is the first diaphragm type compressor 2, opens the first delay tank and is vented electric diaphragm valve 21, gas is through the second electricity of falling case Dynamic diaphragm valve 18 enters the second diaphragm type compressor 3, enters the second cooler 5 and the second gas after the compression of the second diaphragm type compressor 3 Separator 7 is cooled down and is dried, and screens out the decay in stand-by state by the pressure sensor that delay tank is equipped with Case such as third delay tank 10, is then turned on the 6th delay tank air inlet electric diaphragm valve 31, useless after moisture trap 7 is dry Gas enters in third delay tank 10 after second one-way valve 60 and the 6th delay tank air inlet electric diaphragm valve 31, starts storage and declines Become, subsequent processing and above-mentioned process always, repeat no more.
Finally, it should be noted that the above specific embodiment is only to illustrate the art of this patent scheme rather than limits, to the greatest extent Pipe is described in detail this patent referring to preferred embodiment, those skilled in the art should understand that, it can be to this The technical solution of patent is modified or replaced equivalently, should all without departing from the spirit and scope of the art of this patent scheme Cover in the scope of the claims of this patent.

Claims (10)

1. a kind of Spent Radioactive gas processing system of sea floating nuclear power platform, it is characterised in that: including surge tank (1), diaphragm Compressor, cooler, moisture trap, delay tank, iodine adsorption cleaning unit (11), blower (12) and chimney (13), it is described slow The entrance for rushing tank (1) is connected with the hydrogeneous exhaust pipe (A) of up-stream system, and outlet is connected with the air inlet of diaphragm type compressor, The exhaust pipe of the diaphragm type compressor is sequentially connected in series with cooler, moisture trap, the cooling of the diaphragm type compressor, cooler The both ends of water pipe are connected with the input of component cooling water system, efferent duct respectively, the exhaust outlet of the moisture trap and decay Case air inlet is connected, and the exhaust pipe of the delay tank is connected with iodine adsorption cleaning unit (11), the iodine adsorption cleaning unit (11) rear end is sequentially connected in series blower (12), flowmeter (92), finally leads to chimney (13), carries out high point discharge.
2. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 1, it is characterised in that: described Diaphragm type compressor includes the first diaphragm type compressor (2) parallel with one another, mutual backup and the second diaphragm type compressor (3), and described The exhaust pipe of one diaphragm type compressor (2) is sequentially connected in series with the first cooler (4), the first moisture trap (6), second diaphragm The exhaust pipe and the second cooler (5), the second moisture trap of compressor (3) are sequentially connected in series (7).
3. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 2, it is characterised in that: described The cooling water pipe of first diaphragm type compressor (2) and the second diaphragm type compressor (3), the first cooler (4) and the second cooler (5) Parallel with one another, water inlet is connected with component cooling water system water inlet pipe (C1), the return pipe of water outlet and component cooling water system (C2) it is connected, cooling by component cooling water system progress central water supply, the rear end of water inlet pipe (C1) and return pipe (C2) is set respectively Cold in-water temperature sensor (74) and cooling water return water temperature sensor (75) are carried out for the temperature to component cooling water Monitoring.
4. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 2, it is characterised in that: described Delay tank includes the first delay tank (8), the second delay tank (9) and third delay tank (10) of mutual backup, the gas-water separation The exhaust outlet of device is connected with the first delay tank (8), the second delay tank (9) and third delay tank (10), the first delay tank (8), It is respectively equipped with pressure sensor, temperature sensor and liquid level sensor on second delay tank (9) and third delay tank (10), respectively Pressure, temperature, liquid level are monitored, first delay tank (8), the second delay tank (9) and third delay tank (10) row Tracheae is in parallel, circulates by delay tank exhaust electric diaphragm valve (33) and iodine adsorption cleaning unit (11).
5. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 1, it is characterised in that: described Iodine adsorption cleaning unit (11) includes electric heater, prefilter, high efficiency particulate air filter, iodine adsorber and postposition high efficiency particulate air filter, Electric heater is for being dried exhaust gas, the particle and aerosol that prefilter and high efficiency particulate air filter are used to go in removing exhaust gas, Iodine adsorber is used for the methyl iodide and elemental iodine gone in removing exhaust gas, and postposition high efficiency particulate air filter is used to retain the active carbon of air-flow carrying Particle.
6. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 1, it is characterised in that: also wrap Include nitrogen sparge tube road, the air inlet and nitrogen source capsule (B) on the nitrogen sparge tube road, by nitrogen pipeline electric diaphragm valve (35) air inlet and after the first pressure reducing valve (71), with surge tank (1), diaphragm type compressor, cooler, moisture trap and delay tank Pipe is connected.
7. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 4, it is characterised in that: also wrap Sampling line is included, first is respectively arranged on first delay tank (8), the second delay tank (9) and third delay tank (10) and takes Sample electric diaphragm valve (24), the second sampling electric diaphragm valve (28), third sampling electric diaphragm valve (32), sampling line merges into One the second pressure reducing valve of road (72) leads to the sampling system reception pipe (E) of nuclear power platform, is sampled point to ageing effect Analysis.
8. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 6, it is characterised in that: described Oxygen content analyzer (73) are provided on surge tank (1).
9. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 4, it is characterised in that: described The first delay tank is respectively arranged on first delay tank (8), the second delay tank (9) and third delay tank (10) and surge tank (1) Liquid level sensor (89), the second delay tank liquid level sensor (90), third delay tank liquid level sensor (91), surge tank liquid level pass Sensor (88), the first delay tank liquid level sensor (89), the second delay tank liquid level sensor (90), third delay tank liquid level Sensor (91), the collection value for buffering tank level indicator (89) be when reaching threshold value, is respectively arranged at the first delay tank (8), the Two delay tanks (9), third delay tank (10) and surge tank (1) bottom first release water electric diaphragm valve (47), second release Water electric diaphragm valve (44) unlatching that water electric diaphragm valve (48), third release water electric diaphragm valve (49) and surge tank is released, the Liquid in one delay tank (8), the second delay tank (9) and third delay tank (10) and surge tank (1) is discharged under the effect of gravity Liquid Radwaste Treatment reception pipe (D).
10. the Spent Radioactive gas processing system of floating nuclear power platform in sea according to claim 4, it is characterised in that: institute State the first delay tank (8), the second delay tank (9) and third delay tank (10) respectively by the first electric diaphragm valve of falling case (16), Second electric diaphragm valve of falling case (18) is connected with the air inlet pipe of the first diaphragm type compressor (2) and the second diaphragm type compressor (3).
CN201910098642.2A 2019-01-31 2019-01-31 The Spent Radioactive gas processing system of marine floating nuclear power platform Pending CN109712738A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201910098642.2A CN109712738A (en) 2019-01-31 2019-01-31 The Spent Radioactive gas processing system of marine floating nuclear power platform

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201910098642.2A CN109712738A (en) 2019-01-31 2019-01-31 The Spent Radioactive gas processing system of marine floating nuclear power platform

Publications (1)

Publication Number Publication Date
CN109712738A true CN109712738A (en) 2019-05-03

Family

ID=66263472

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201910098642.2A Pending CN109712738A (en) 2019-01-31 2019-01-31 The Spent Radioactive gas processing system of marine floating nuclear power platform

Country Status (1)

Country Link
CN (1) CN109712738A (en)

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4045539A (en) * 1974-02-01 1977-08-30 Hitachi, Ltd. Process for decontaminating gas containing radioactive iodine
JPH0968591A (en) * 1995-08-31 1997-03-11 Toshiba Corp Method of disposing radioactive gas waste
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
CN104143368A (en) * 2014-08-12 2014-11-12 中广核工程有限公司 Nuclear power station radioactive waste gas treatment system
CN206097936U (en) * 2016-08-29 2017-04-12 江西怡杉环保股份有限公司 Waste gas treatment system is stored in pressurization
CN107833648A (en) * 2017-11-01 2018-03-23 中国船舶重工集团公司第七〇九研究所 The more control area vacuum control systems of ocean nuclear power platform and control method
JP2018169252A (en) * 2017-03-29 2018-11-01 三菱重工業株式会社 Storage container maintenance facility and method for maintaining storage container
CN209607429U (en) * 2019-01-31 2019-11-08 中国船舶重工集团公司第七一九研究所 The Spent Radioactive gas processing system of marine floating nuclear power platform

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4045539A (en) * 1974-02-01 1977-08-30 Hitachi, Ltd. Process for decontaminating gas containing radioactive iodine
JPH0968591A (en) * 1995-08-31 1997-03-11 Toshiba Corp Method of disposing radioactive gas waste
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
CN104143368A (en) * 2014-08-12 2014-11-12 中广核工程有限公司 Nuclear power station radioactive waste gas treatment system
CN206097936U (en) * 2016-08-29 2017-04-12 江西怡杉环保股份有限公司 Waste gas treatment system is stored in pressurization
JP2018169252A (en) * 2017-03-29 2018-11-01 三菱重工業株式会社 Storage container maintenance facility and method for maintaining storage container
CN107833648A (en) * 2017-11-01 2018-03-23 中国船舶重工集团公司第七〇九研究所 The more control area vacuum control systems of ocean nuclear power platform and control method
CN209607429U (en) * 2019-01-31 2019-11-08 中国船舶重工集团公司第七一九研究所 The Spent Radioactive gas processing system of marine floating nuclear power platform

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
李建业等: ""含氢废气处理系统运行缺陷及风险分析"", 《科技资讯》, no. 29, pages 114 - 116 *
祝杰等: ""浅谈核电放射性废气净化技术"", 《广东化工》, vol. 43, no. 20, pages 124 - 126 *

Similar Documents

Publication Publication Date Title
CN103474121B (en) Nuclear power station Spent Radioactive gas processing system
CN104143368B (en) Nuclear power station radioactive waste gas treatment system
CN101847456A (en) Waste gas treatment method of nuclear power plant and treatment device thereof
CN110444309B (en) Nuclear facility radioactive process waste gas treatment system
CN203456108U (en) Radioactive waste gas treatment system for nuclear power station
CN209607429U (en) The Spent Radioactive gas processing system of marine floating nuclear power platform
CN106178817A (en) A kind of extensive carbon dioxide capture system and capture method
CN109166641B (en) Low-level radioactive waste gas treatment system in lead bismuth reactor
CN101814326A (en) Pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment
CN102226949B (en) Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases
CN211629222U (en) Fuel cell system and exhaust hydrogen purging system using stack waste gas
CN110124443B (en) Organic waste gas recycling device and method
CN109712738A (en) The Spent Radioactive gas processing system of marine floating nuclear power platform
CN212303100U (en) Emergency device for treating nuclear leakage pollutants
CN206131682U (en) Spentnuclear fuel storage and transportation container aerifys drying device
CN206131613U (en) Spentnuclear fuel storage and transportation container vacuum drying and helium charging unit
CN207317085U (en) A kind of indoor air environment ecology reconstruction system
CN215730900U (en) Radioactive waste gas treatment system for nuclear facility
CN207002252U (en) A kind of fast oxygen gas preparation facilities
CN112722222A (en) Kilometer-level hydrogen-oxygen saturation submersible external circulation environment control system
CN102479564A (en) Novel complete device for room-temperature delay treatment of highly radioactive waste gas of nuclear power station
CN208372695U (en) A kind of air filter that self limiting temperature adapts to
CN107444795B (en) Industrial wastewater accident tank waste gas collection device and method
CN215155554U (en) Kilometer-level hydrogen-oxygen saturation submersible external circulation environment control system
CN115193216B (en) Nuclear power station waste gas treatment system based on activated carbon delay bed and application method thereof

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination