CN105301624A - Nuclear power plant radioactive exudation monitoring system - Google Patents
Nuclear power plant radioactive exudation monitoring system Download PDFInfo
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- CN105301624A CN105301624A CN201510831416.2A CN201510831416A CN105301624A CN 105301624 A CN105301624 A CN 105301624A CN 201510831416 A CN201510831416 A CN 201510831416A CN 105301624 A CN105301624 A CN 105301624A
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Abstract
Provided is a nuclear power plant radioactive exudation monitoring system which comprises an airborne radioactive exudation monitoring system. The airborne radioactive exudation monitoring system comprises a heating unit. The heating unit is used for heating gases in a part, outside a chimney, of a sampling pipeline where an aerosol and iodine monitor in the airborne radioactive exudation monitoring system is located, and a part, outside a chimney, of a sampling pipeline where an aerosol and iodine sampler is located. The nuclear power plant radioactive exudation monitoring system may prevent aerosol and iodine steam condensation caused by a decrease in ambient temperature and may increase aerosol and iodine acquisition efficiency. Further, a compressor is arranged on the upstream of an inert gas sampling bottle so as to increase gas concentration. In a high radioactivity monitoring system, a lead shielding device is arranged outside the inert gas sampling bottle and the aerosol and iodine sampler in order to improve protection of workers against radiation. A liquid radioactive exudation monitoring system is improved, simplified in structure, and decreased in fault links. A flowmeter is provided in order to compute total discharge activity.
Description
Technical field
The present invention relates to nuclear power station field, particularly relate to a kind of nuclear power plant radioactive effluent monitoring system.
Background technology
Nuclear power plant's airborne radioactivity effluent and Radioactive Liquid Effluent all have a corresponding year emission control limit value, wherein, airborne radioactivity effluent comprise gasoloid, iodine, inert gas,
14c,
3h, Radioactive Liquid Effluent comprises
3h,
14c and all the other nucleic.
With reference to figure 1, gaseous effluent passes through nuclear island factory building gas shaft to environment continuous blow-down, sampling head 1 continuous sampling effluent is set in chimney 10, aerosol monitoring instrument 2, iodine monitor 3, lower range inert gas monitor 4 are monitor gasoloid, iodine, inert gas activity concentration continuously under nuclear power plant's normal running (operation) conditions respectively, and high range inert gas monitor 5 is for high radioactivity inert gas activity concentration after Real-Time Monitoring nuclear power plant accident and accident; The sampling thief 6 of gasoloid and iodine, inert gas sampling bottle 7,
3h sampling thief 8,
14c sampling thief 9 send laboratory to analyze for corresponding sample of sampling, and only have aerosol monitoring instrument 2, iodine monitor 3 arranges bypass branch, be convenient to safeguard separately gasoloid or iodine monitoring branch road.Its major defect is sample gas from when in chimney 10, sampling pipeline transfers to chimney 10 external pipeline, because environment temperature declines, can cause the condensation of water vapour, iodine steam, reduces gasoloid, iodine collecting efficiency.In addition, inert gas sampling uses normal pressure gas cylinder canning means, and according to operational experience feedback, when nuclear power plant normally runs, inert gas activity concentration is lower than lab analysis device measuring lower limit (10
2bq/m
3), cause measuring actual activity concentration; Gasoloid, iodine, inert gas sampling thief lack personnel's Radiation Exposure, the sampling of high radiation sample under inapplicable emergency conditions.
With reference to figure 2, liquid effluent adopts slot type discharge, low-activity waste liquid to be discharged is temporary a period of time in nuclear island or conventional island waste liquid hold-up vessel 16, meet emission request then start discharge as room is by experiment analyzed, this monitoring system adopts off-line sampling monitoring mode, discharging of waste liquid pipeline 17 is provided as the sampling pipeline of branch road, sampling pipeline is arranged and measures chamber 11, flowmeter 12, sampling pump 13 and flow control valve 14, measure chamber 11 for measuring fluid to be measured activity concentration, flowmeter 12 is for monitoring cutout fault.For preventing lab analysis from makeing mistakes, arrange radiation monitor, when discharging of waste liquid activity concentration exceedes setting value, monitor chain cut out discharging of waste liquid isolation valve 15, prevents discharge beyond standards; Measuring between chamber 11 and flowmeter 12 and wash-down water interface is set, measuring chamber 11, sampling pipeline, sampling pump 13 for rinsing; Sampling pipeline and sampling pump 13 arrange hydrophobic pipeline, for emptying sampling pipeline and sampling pump 13, are convenient to service equipment, and provide drain outlet when flushing device.This monitoring system complex structure, safeguards loaded down with trivial details, is unfavorable for reducing maintainer's occupational exposure; And waste liquid activity concentration can only be monitored, can not calculate and always discharge activity; Measuring chamber 11 can not be naturally emptying, easily accumulates radioactive contamination, can not realize background bales catch and remove, affect measurement accuracy when next time discharges; The false alarm under non-discharge state can not be avoided.
Summary of the invention
The technical problem to be solved in the present invention is, for the above-mentioned defect of prior art, provides a kind of nuclear power plant radioactive effluent monitoring system.
The technical solution adopted for the present invention to solve the technical problems is: construct a kind of nuclear power plant radioactive effluent monitoring system, comprise the airborne radioactivity effluent monitoring system for monitoring the airborne radioactivity effluent in chimney, described airborne radioactivity effluent monitoring system comprises:
Heating unit, pipe gas for the part be positioned at outside chimney of the sampling conduit at the monitor place to the gasoloid in described airborne radioactivity effluent monitoring system and iodine heats, and heats the pipe gas of the part be positioned at outside chimney of the sampling conduit at the sampling thief place of gasoloid and iodine.
In nuclear power plant of the present invention radioactive effluent monitoring system, described airborne radioactivity effluent monitoring system comprises separate:
Low-activity monitoring system, for starting under power plant's normal operating condition, comprising: extend to the common conduit in chimney, the first pipeline of the gas exhaust duct connected on airduct, the second pipe connecting described common conduit and the first pipeline, the 3rd pipeline that is arranged in parallel with second pipe; First pipeline is provided with lower range inert gas monitor, second pipe is provided with aerosol monitoring instrument and iodine monitor, and aerosol monitoring instrument is positioned at the upstream of iodine monitor, the sampling thief of the 3rd install pipeline gasoloid and iodine;
High radioactivity monitoring system, start during for exceeding the monitoring capability of low-activity monitoring system at radioactive level, comprise: to extend in chimney and the main pipeline be connected with another gas exhaust duct on airduct, described main pipeline is provided with sampling thief and the high range inert gas monitor of gasoloid and iodine, and the sampling thief of gasoloid and iodine is positioned at the upstream of high range inert gas monitor;
Wherein, the pipe gas of the part that described heating unit is used for being positioned at described common conduit part outside chimney, the first pipeline, second pipe, the 3rd pipeline, described main pipeline are positioned at outside chimney heats.
In nuclear power plant of the present invention radioactive effluent monitoring system, described heating unit comprises:
Electrical heating wire, is wrapped on corresponding pipeline, for the gas-heated in pipeline;
Temperature acquisition is popped one's head in, and is arranged on evenly and at intervals and is wound with in the pipeline of electrical heating wire, for collecting temperature signal;
Thermal treatment temperature control device, pops one's head in electrical heating wire and temperature acquisition respectively and is connected, and is vented maximum temperature for the heating controlling electrical heating wire according to the temperature signal of temperature acquisition probe feedback to make the heating temperatures be wound with in the pipeline of electrical heating wire to chimney.
In nuclear power plant of the present invention radioactive effluent monitoring system, described low-activity monitoring system also comprises the 4th pipeline that input end is connected to described common conduit, output terminal is connected to an inert gas sampling bottle, and the position being positioned at inert gas sampling bottle upstream of described 4th pipeline is provided with compressor.
In nuclear power plant of the present invention radioactive effluent monitoring system, described 4th pipeline is also provided with the particle filter being positioned at described upstream of compressor, the isolation valve being positioned at particle filter upstream.
In nuclear power plant of the present invention radioactive effluent monitoring system, described first pipeline is also provided with the sampling pump being positioned at lower range inert gas monitor downstream.
In nuclear power plant of the present invention radioactive effluent monitoring system, described low-activity monitoring system also comprises the 5th pipeline that input end is connected to described common conduit, output terminal is connected to gas exhaust duct, six pipeline in parallel with the 5th pipeline; Described 5th pipeline is provided with
3h sampling thief, described 6th pipeline is provided with
14c sampling thief.
In nuclear power plant of the present invention radioactive effluent monitoring system, described in
3the both sides of H sampling thief arrange and arrange an isolation valve, described in
14the both sides of C sampling thief arrange and arrange an isolation valve.
In nuclear power plant of the present invention radioactive effluent monitoring system, the aerosol monitoring instrument of described low-activity monitoring system, iodine monitor, lower range inert gas monitor are provided with bypass duct; The gasoloid of described high radioactivity monitoring system and the sampling thief of iodine, high range inert gas monitor are provided with bypass duct;
Be respectively arranged with two isolation valves on the bypass duct of described aerosol monitoring instrument and on the bypass duct of the sampling thief of gasoloid and iodine and be positioned at the particle filter in the middle of two isolation valves, the bypass duct of iodine monitor, lower range inert gas monitor, high range inert gas monitor is respectively arranged with an isolation valve.
In nuclear power plant of the present invention radioactive effluent monitoring system, described first pipeline is provided with two isolation valves, described lower range inert gas monitor is between these two isolation valves; Second pipe is provided with four isolation valves, aerosol monitoring instrument is positioned in the middle of the first two isolation valve, and iodine monitor is positioned in the middle of latter two isolation valve; 3rd pipeline is provided with two isolation valves of the sampling thief both sides being positioned at gasoloid and iodine.
In nuclear power plant of the present invention radioactive effluent monitoring system, described main pipeline is also provided with the sampling pump being positioned at high range inert gas monitor downstream and the isolation valve being positioned at sampling pump downstream, and main pipeline be positioned at this sampling pump downstream and the position being positioned at these isolation valve both sides connects two joints, these two joints are for connecting inert gas sampling bottle.
In nuclear power plant of the present invention radioactive effluent monitoring system, outside described inert gas sampling bottle, lead shield device is set.
In nuclear power plant of the present invention radioactive effluent monitoring system, outside described lead shield device, be laid with portable dose rate instrument.
In nuclear power plant of the present invention radioactive effluent monitoring system, outside the gasoloid on described main pipeline and the sampling thief of iodine, lead shield device is set.
In nuclear power plant of the present invention radioactive effluent monitoring system, described lead shield device extenal fixation has at least one dose rate monitor.
In nuclear power plant of the present invention radioactive effluent monitoring system, described nuclear power plant radioactive effluent monitoring system also comprises carries out the Radioactive Liquid Effluent monitoring system of monitoring for liquid towards radioactive effluent, and described Radioactive Liquid Effluent monitoring system comprises:
Discharge tube, is connected to waste liquid memory storage;
Discharging of waste liquid pump, is arranged on discharge tube;
Measure chamber, to be arranged on discharge tube and to be positioned at discharging of waste liquid pump downstream;
Activity concentration measuring instrument, is arranged on and measures in chamber, for exporting the activity concentration signal of waste liquid;
Flowmeter, to be arranged on discharge tube and to be positioned at and measure chamber downstream, for delivery rate signal;
Discharge isolation valve, to be arranged on discharge tube and to be positioned at flowmeter downstream;
Monitor, is connected with activity concentration measuring instrument and flowmeter respectively, always discharges activity for calculating according to described activity concentration signal and flow signal, and control discharge isolation valve cuts out and starts warning when total discharge activity exceedes activity threshold value.
In nuclear power plant of the present invention radioactive effluent monitoring system, described flowmeter also for flow lower than during flow threshold send alerting signal to monitor; Described monitor is also for terminating during judging current emissions when receiving alerting signal and closing warning function.
In nuclear power plant of the present invention radioactive effluent monitoring system, described monitor is also for after receiving alerting signal, total discharge activity end during current emissions extremely being started to calculate during this period of time between next draining period as background radiation data, and deducts described background radiation data when calculating the total discharge activity between next draining period.
In nuclear power plant of the present invention radioactive effluent monitoring system, described discharge tube is positioned at the height of part lower than described measurement chamber in described measurement chamber downstream.
Implement nuclear power plant of the present invention radioactive effluent monitoring system, there is following beneficial effect: the present invention increases heating unit, the pipe gas being positioned at the part be positioned at outside chimney of the sampling conduit at the sampling thief place of part outside chimney and gasoloid and iodine of the sampling conduit at the monitor place of the gasoloid in airborne radioactivity effluent monitoring system and iodine is heated, therefore can effectively avoid due to environment temperature decline and cause gasoloid, iodine steam condensation, improve gasoloid, iodine collecting efficiency;
Further, airborne radioactivity effluent Monitoring System is separate low-activity monitoring system and high radioactivity monitoring system by the present invention; Wherein, the inert gas sampling bottle upstream in low-activity monitoring system arranges compressor, therefore improves gas concentration, adapts to laboratory equipment analysis ability; Wherein, in high radioactivity monitoring system, lead shield device is set outside the sampling thief of inert gas sampling bottle and gasoloid and iodine, increases the protection to personnel's radiation, the sampling of high radiation sample under being suitable for emergency conditions; Further, liquid towards radioactive effluent monitoring system of the present invention is also improved, and adopts Embedded monitoring mode, simplifies the structure of monitoring system, decrease failsafe link; By arranging flowmeter, achieving and always discharging Activity Calculation; By the monitoring identification emissions status to flow, and then avoid the false alarm under non-discharge state; Same, by identifying emissions status, realize the measurement function of background radiation data under non-discharge state, and then background bales catch when achieving discharge next time is except function; By taking rational arrangement, ensureing to measure waste liquid in chamber naturally emptying, reducing the impact of polluting measuring.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the structural representation of traditional airborne radioactivity effluent monitoring system;
Fig. 2 is the structural representation of traditional Radioactive Liquid Effluent monitoring system;
Fig. 3 is the structural representation of the airborne radioactivity effluent monitoring system in the present invention;
Fig. 4 is the structural representation of the Radioactive Liquid Effluent monitoring system in the present invention.
Embodiment
In order to there be understanding clearly to technical characteristic of the present invention, object and effect, now contrast accompanying drawing and describe the specific embodiment of the present invention in detail.
The Radioactive Liquid Effluent monitoring system that nuclear power plant of the present invention radioactive effluent monitoring system comprises the airborne radioactivity effluent monitoring system for monitoring airborne radioactivity effluent and monitors for liquid towards radioactive effluent.
Wherein, described airborne radioactivity effluent monitoring system comprises heating unit, the pipe gas that described heating unit is used for the part be positioned at outside chimney of the sampling conduit at the monitor place to the gasoloid in described airborne radioactivity effluent monitoring system and iodine heats, and heats the pipe gas of the part be positioned at outside chimney of the sampling conduit at the sampling thief place of gasoloid and iodine.Therefore can effectively avoid due to environment temperature decline and cause gasoloid, iodine steam condensation, improve gasoloid, iodine collecting efficiency.
Wherein, described heating unit comprises: electrical heating wire, temperature acquisition probe, thermal treatment temperature control device.
Electrical heating wire, is wrapped on corresponding pipeline, for the gas-heated in pipeline;
Temperature acquisition is popped one's head in, and is arranged on evenly and at intervals and is wound with in the pipeline of electrical heating wire, for collecting temperature signal;
Thermal treatment temperature control device, pops one's head in electrical heating wire and temperature acquisition respectively and is connected, and is vented maximum temperature for the heating controlling electrical heating wire according to the temperature signal of temperature acquisition probe feedback to make the heating temperatures be wound with in the pipeline of electrical heating wire to chimney.
In addition, double-skin duct can be adopted to realize by the pipeline heated, between the skin and internal layer of pipeline, arrange electrical heating wire, preferably, taking cost into account, electrical heating wire is directly wrapped in outside pipeline by the present invention.
Introduce the airborne radioactivity effluent monitoring system in nuclear power plant's radioactive effluent monitoring system and Radioactive Liquid Effluent monitoring system below respectively.
Fig. 3 is the structural representation of the airborne radioactivity effluent monitoring system in the present invention.
Described airborne radioactivity effluent monitoring system comprise separate low-activity monitoring system 100 for starting under power plant's normal operating condition and for exceed low-activity monitoring system 100 at radioactive level monitoring capability time the high radioactivity monitoring system 200 that starts.
Wherein, low-activity monitoring system 100 mainly under power plant's normal operating condition to gasoloid, iodine, inert gas,
3h,
14c samples, and carries out on-line monitoring to gasoloid, iodine, inert gas.The gasoloid that high radioactivity monitoring system 200 is mainly right after accident, iodine, inert gas are sampled and are monitored.
With reference to figure 3, described low-activity monitoring system 100 comprises: extend to the common conduit 90 be connected with a sampling head 60 in chimney, connect the first pipeline 91 of the gas exhaust duct 41 on airduct 50, connect the second pipe 92 of described common conduit 90 and the first pipeline 91, the 3rd pipeline 93 be arranged in parallel with second pipe 92, input end is connected to described common conduit 90 and output terminal is connected to the 4th pipeline 94 of an inert gas sampling bottle 441, input end is connected to described common conduit 90 and output terminal is connected to the 5th pipeline 95 of gas exhaust duct 41, six pipeline 96 in parallel with the 5th pipeline.
First pipeline 91 is provided with two isolation valves G1, G2, is positioned at the sampling pump 411 in two isolation valve G1, G2 downstreams, and the lower range inert gas monitor 103 between these two isolation valves G1, G2; And lower range inert gas monitor 103 is also provided with bypass duct, concrete, bypass duct is arranged an isolation valve G3, the two ends of bypass duct connect the upstream of the isolation valve G1 being positioned at upstream respectively, are positioned at the downstream of the isolation valve G2 in downstream.
Second pipe 92 is provided with four isolation valves G4, G5, G6, G7, is positioned at the aerosol monitoring instrument 101 that the first two isolation valve G4, G5 of upstream are middle, be positioned at the iodine monitor 102 that latter two isolation valve G6, the G7 in downstream are middle; Same, described aerosol monitoring instrument 101, iodine monitor 102 are provided with bypass duct.The bypass duct of aerosol monitoring instrument 101 connects the position between the upstream of first isolation valve G4 and second isolation valve G5 and the 3rd isolation valve G6.The bypass duct of iodine monitor 102 connects the downstream of position between second isolation valve G5 and the 3rd isolation valve G6 and the 4th isolation valve G7.Wherein, the bypass duct of described aerosol monitoring instrument 101 is provided with two isolation valves G8, G9 and is positioned at the particle filter 431 in the middle of two isolation valves G8, G9, the bypass duct of iodine monitor 102 is provided with isolation valve G10.
3rd pipeline 93 arranges two isolation valves G11, G12 and the sampling thief 421 of the gasoloid that is positioned in the middle of these two isolation valves G11, G12 and iodine, and the sampling thief 421 of gasoloid and iodine is actually aerosol sampler and iodine sampling thief to be packaged together and forms.
Isolation valve under normal circumstances on bypass duct is all cut out, when needs keep in repair corresponding monitor or sampling thief, monitor or sampling thief place pipeline can be closed, open the isolation valve on the bypass duct corresponding to it, so would not affect sampling or the monitoring of other gases.
4th pipeline 94 is also provided with particle filter 432 in described compressor 106 upstream and at the isolation valve G13 of particle filter 432 upstream, the compressor 106 between particle filter 432 and inert gas sampling bottle 441.
5th pipeline 95 arranged two isolation valves G14, G15 and be positioned in the middle of these two isolation valves G14, G15
3h sampling thief 104.
6th pipeline 96 arranged two isolation valves G16, G17 and be positioned in the middle of these two isolation valves G16, G17
14c sampling thief 105.
Wherein, described common conduit 90 be positioned at part outside chimney, the first pipeline 91, second pipe 91, the 3rd pipeline 93 outside be all wound with electrical heating wire, and interval is evenly provided with temperature acquisition probe in these pipelines, temperature acquisition probe is connected to the thermal treatment temperature control device of the described electrical heating wire heating of control, and the heating temperatures that described thermal treatment temperature control device is used for controlling in this part pipeline according to the temperature signal of temperature acquisition probe feedback is vented maximum temperature to chimney.
Wherein, described high radioactivity monitoring system 200 comprises: extend to the main pipeline 30 be connected with another sampling head 61 in chimney, the output terminal of main pipeline 30 is connected with another gas exhaust duct 42 on airduct 50.Described main pipeline 30 is provided with sampling thief 422 and the high range inert gas monitor 202 of gasoloid and iodine, and the sampling thief 422 of gasoloid and iodine is positioned at the upstream of high range inert gas monitor 202, the part that described main pipeline 30 is positioned at outside chimney is all wound with electrical heating wire.
Main pipeline 30 is arranged five isolation valves G18, G19, G20, G21, G22, the sampling thief 422 of gasoloid and iodine is positioned in the middle of first isolation valve G18 and second isolation valve G19, high range inert gas monitor 202 is positioned in the middle of the 3rd isolation valve G20 and a 4th isolation valve G21, and sampling pump 412 is positioned in the middle of the 4th isolation valve G21 and a 5th isolation valve G22.Being positioned at this sampling pump 412 downstream and being positioned at the 5th position isolating G22 valve both sides of main pipeline 30 connects two joints 201, and these two joints 201 are for connecting inert gas sampling bottle 442.
Preferably, outside described inert gas sampling bottle 442, lead shield device is set, outside described lead shield device, is laid with portable dose rate instrument 203.When inert gas irradiation dose measured by needs, portable dose rate instrument 203 is positioned over the outer image data of lead shield device.
Preferably, the sampling thief 422 of gasoloid and iodine is outer also arranges lead shield device.Described lead shield device extenal fixation has at least one dose rate monitor 204.Dose rate monitor 204 can be fixed on lead shield device, with the irradiation dose of real time on-line monitoring gasoloid and iodine.
Same, the gasoloid of described high radioactivity monitoring system 200 and the sampling thief 422 of iodine, high range inert gas monitor 202 are provided with bypass duct.The bypass duct of the sampling thief 422 of gasoloid and iodine connects the position between the position of the upstream of first isolation valve G18 and second isolation valve G19 and the 3rd isolation valve G20, and the bypass duct of high range inert gas monitor 202 connects position between second isolation valve G19 and the 3rd isolation valve G20 and the 4th position between isolation valve G21 and sampling pump 412.The bypass duct of the sampling thief 422 of gasoloid and iodine is respectively arranged with two isolation valves G23, G24 and is positioned at the particle filter 433 in the middle of two isolation valves G23, G24, the bypass duct of high range inert gas monitor 202 is provided with an isolation valve G25.
Because inert gas sampling bottle 441 upstream arranges compressor 106, therefore improve gas concentration, adapt to laboratory equipment analysis ability; Owing to arranging lead shield device in high radioactivity monitoring system 200 outside the sampling thief 422 of inert gas sampling bottle 442 and gasoloid and iodine, increase the protection to personnel's radiation, the sampling of high radiation sample under being suitable for emergency conditions.
In the present invention, low-activity monitoring system 100 and high radioactivity monitoring system 200 take independently sampling head 60,61 respectively, certainly in theory also can a public sampling head, but because the requirement of low-activity monitoring system 100 and high radioactivity monitoring system 200 pairs of flows is different, namely sampling pump 411 is different with the running parameter of 412, so preferred, two systems adopt an independently sampling head separately.
Fig. 4 is the structural representation of the Radioactive Liquid Effluent monitoring system in the present invention.
Described Radioactive Liquid Effluent monitoring system comprises monitor (not shown) and is connected to the discharge tube 60 of waste liquid memory storage 301, waste liquid memory storage 301 can be waste liquid hold-up vessel, described discharge tube 60 is provided with: discharging of waste liquid pump 302, be positioned at discharging of waste liquid pump 302 downstream measurement chamber 303, be positioned at the flowmeter 304 of measuring chamber 303 downstream and be positioned at the draining isolation valve 305 in flowmeter 304 downstream, measure in chamber 303 and be provided with activity concentration measuring instrument, described activity concentration measuring instrument, flowmeter 304 are connected to described monitor; Described activity concentration measuring instrument for exporting the activity concentration signal of waste liquid to monitor, described flowmeter 304 for delivery rate signal to monitor; Described monitor is used for calculating total discharge activity according to described activity concentration signal and flow signal and controlling draining isolation valve 305 when total discharge activity exceedes activity threshold value closing and starting warning.
Because Radioactive Liquid Effluent is all generally low-activity waste liquid, so the present invention does not adopt branch road to measure, but directly monitoring equipment is set on main pipeline 30, namely adopts Embedded monitoring mode, simplify the structure of monitoring system, decrease failsafe link.And by arranging flowmeter 304, achieving and always discharging Activity Calculation.
Preferably, described flowmeter 304 also for flow lower than during flow threshold send alerting signal to monitor; Described monitor is also for terminating during judging current emissions when receiving alerting signal and closing warning function.
Preferably, described monitor is also for after receiving alerting signal, total discharge activity end during current emissions extremely being started to calculate during this period of time between next draining period as background radiation data, and deducts described background radiation data when calculating the total discharge activity between next draining period.
By the monitoring identification emissions status to flow, and then avoid the false alarm under non-discharge state; Same, by identifying emissions status, realize the measurement function of background radiation data under non-discharge state, and then background bales catch when achieving discharge next time is except function;
Preferably, described discharge tube 60 is positioned at the height of part lower than described measurement chamber 303 in described measurement chamber 303 downstream.Take this rational arrangement, ensureing to measure waste liquid in chamber 303 naturally emptying, reducing the impact of polluting measuring.
In sum, implement nuclear power plant of the present invention radioactive effluent monitoring system, there is following beneficial effect: the present invention increases heating unit, the pipe gas being positioned at the part be positioned at outside chimney of the sampling conduit at the sampling thief place of part outside chimney and gasoloid and iodine of the sampling conduit at the monitor place of the gasoloid in airborne radioactivity effluent monitoring system and iodine is heated, therefore can effectively avoid due to environment temperature decline and cause gasoloid, iodine steam condensation, improve gasoloid, iodine collecting efficiency; Further, airborne radioactivity effluent Monitoring System is separate low-activity monitoring system and high radioactivity monitoring system by the present invention; Wherein, the inert gas sampling bottle upstream in low-activity monitoring system arranges compressor, therefore improves gas concentration, adapts to laboratory equipment analysis ability; Wherein, in high radioactivity monitoring system, lead shield device is set outside the sampling thief of inert gas sampling bottle and gasoloid and iodine, increases the protection to personnel's radiation, the sampling of high radiation sample under being suitable for emergency conditions; Further, liquid towards radioactive effluent monitoring system of the present invention is also improved, and adopts Embedded monitoring mode, simplifies the structure of monitoring system, decrease failsafe link; By arranging flowmeter, achieving and always discharging Activity Calculation; By the monitoring identification emissions status to flow, and then avoid the false alarm under non-discharge state; Same, by identifying emissions status, realize the measurement function of background radiation data under non-discharge state, and then background bales catch when achieving discharge next time is except function; By taking rational arrangement, ensureing to measure waste liquid in chamber naturally emptying, reducing the impact of polluting measuring.
By reference to the accompanying drawings embodiments of the invention are described above; but the present invention is not limited to above-mentioned embodiment; above-mentioned embodiment is only schematic; instead of it is restrictive; those of ordinary skill in the art is under enlightenment of the present invention; do not departing under the ambit that present inventive concept and claim protect, also can make a lot of form, these all belong within protection of the present invention.
Claims (15)
1. nuclear power plant's radioactive effluent monitoring system, comprising the airborne radioactivity effluent monitoring system for monitoring the airborne radioactivity effluent in chimney, it is characterized in that, described airborne radioactivity effluent monitoring system comprises:
Heating unit, pipe gas for the part be positioned at outside chimney of the sampling conduit at the monitor place to the gasoloid in described airborne radioactivity effluent monitoring system and iodine heats, and heats the pipe gas of the part be positioned at outside chimney of the sampling conduit at the sampling thief place of gasoloid and iodine.
2. nuclear power plant according to claim 1 radioactive effluent monitoring system, is characterized in that, described airborne radioactivity effluent monitoring system comprises separate:
Low-activity monitoring system, for starting under power plant's normal operating condition, comprising: extend to the common conduit in chimney, the first pipeline of the gas exhaust duct connected on airduct, the second pipe connecting described common conduit and the first pipeline, the 3rd pipeline that is arranged in parallel with second pipe; First pipeline is provided with lower range inert gas monitor, second pipe is provided with aerosol monitoring instrument and iodine monitor, and aerosol monitoring instrument is positioned at the upstream of iodine monitor, the sampling thief of the 3rd install pipeline gasoloid and iodine;
High radioactivity monitoring system, start during for exceeding the monitoring capability of low-activity monitoring system at radioactive level, comprise: to extend in chimney and the main pipeline be connected with another gas exhaust duct on airduct, described main pipeline is provided with sampling thief and the high range inert gas monitor of gasoloid and iodine, and the sampling thief of gasoloid and iodine is positioned at the upstream of high range inert gas monitor;
Wherein, the pipe gas of the part that described heating unit is used for being positioned at described common conduit part outside chimney, the first pipeline, second pipe, the 3rd pipeline, described main pipeline are positioned at outside chimney heats.
3. nuclear power plant according to claim 1 radioactive effluent monitoring system, it is characterized in that, described heating unit comprises:
Electrical heating wire, is wrapped on corresponding pipeline, for the gas-heated in pipeline;
Temperature acquisition is popped one's head in, and is arranged on evenly and at intervals and is wound with in the pipeline of electrical heating wire, for collecting temperature signal;
Thermal treatment temperature control device, pops one's head in electrical heating wire and temperature acquisition respectively and is connected, and is vented maximum temperature for the heating controlling electrical heating wire according to the temperature signal of temperature acquisition probe feedback to make the heating temperatures be wound with in the pipeline of electrical heating wire to chimney.
4. nuclear power plant according to claim 2 radioactive effluent monitoring system, it is characterized in that, described low-activity monitoring system also comprises the 4th pipeline that input end is connected to described common conduit, output terminal is connected to an inert gas sampling bottle, and the position being positioned at inert gas sampling bottle upstream of described 4th pipeline is provided with compressor.
5. nuclear power plant according to claim 4 radioactive effluent monitoring system, is characterized in that, described 4th pipeline is also provided with the particle filter being positioned at described upstream of compressor, the isolation valve being positioned at particle filter upstream.
6. nuclear power plant according to claim 2 radioactive effluent monitoring system, is characterized in that, the aerosol monitoring instrument of described low-activity monitoring system, iodine monitor, lower range inert gas monitor are provided with bypass duct; The gasoloid of described high radioactivity monitoring system and the sampling thief of iodine, high range inert gas monitor are provided with bypass duct;
Be respectively arranged with two isolation valves on the bypass duct of described aerosol monitoring instrument and on the bypass duct of the sampling thief of gasoloid and iodine and be positioned at the particle filter in the middle of two isolation valves, the bypass duct of iodine monitor, lower range inert gas monitor, high range inert gas monitor is respectively arranged with an isolation valve.
7. nuclear power plant according to claim 2 radioactive effluent monitoring system, it is characterized in that, described main pipeline is also provided with the sampling pump being positioned at high range inert gas monitor downstream and the isolation valve being positioned at sampling pump downstream, and main pipeline be positioned at this sampling pump downstream and the position being positioned at these isolation valve both sides connects two joints, these two joints are for connecting inert gas sampling bottle.
8. nuclear power plant according to claim 7 radioactive effluent monitoring system, is characterized in that, arranges lead shield device outside described inert gas sampling bottle.
9. nuclear power plant according to claim 8 radioactive effluent monitoring system, is characterized in that, is laid with portable dose rate instrument outside described lead shield device.
10. nuclear power plant according to claim 2 radioactive effluent monitoring system, is characterized in that, arranges lead shield device outside the gasoloid on described main pipeline and the sampling thief of iodine.
11. nuclear power plant according to claim 10 radioactive effluent monitoring systems, is characterized in that, described lead shield device extenal fixation has at least one dose rate monitor.
12. nuclear power plant according to claim 1 radioactive effluent monitoring systems, it is characterized in that, described nuclear power plant radioactive effluent monitoring system also comprises carries out the Radioactive Liquid Effluent monitoring system of monitoring for liquid towards radioactive effluent, and described Radioactive Liquid Effluent monitoring system comprises:
Discharge tube, is connected to waste liquid memory storage;
Discharging of waste liquid pump, is arranged on discharge tube;
Measure chamber, to be arranged on discharge tube and to be positioned at discharging of waste liquid pump downstream;
Activity concentration measuring instrument, is arranged on and measures in chamber, for exporting the activity concentration signal of waste liquid;
Flowmeter, to be arranged on discharge tube and to be positioned at and measure chamber downstream, for delivery rate signal;
Discharge isolation valve, to be arranged on discharge tube and to be positioned at flowmeter downstream;
Monitor, is connected with activity concentration measuring instrument and flowmeter respectively, always discharges activity for calculating according to described activity concentration signal and flow signal, and control discharge isolation valve cuts out and starts warning when total discharge activity exceedes activity threshold value.
13. nuclear power plant according to claim 12 radioactive effluent monitoring systems, is characterized in that, described flowmeter also for flow lower than during flow threshold send alerting signal to monitor; Described monitor is also for terminating during judging current emissions when receiving alerting signal and closing warning function.
14. nuclear power plant according to claim 12 radioactive effluent monitoring systems, it is characterized in that, described monitor is also for after receiving alerting signal, total discharge activity end during current emissions extremely being started to calculate during this period of time between next draining period as background radiation data, and deducts described background radiation data when calculating the total discharge activity between next draining period.
15. nuclear power plant according to claim 12 radioactive effluent monitoring systems, is characterized in that, described discharge tube is positioned at the height of part lower than described measurement chamber in described measurement chamber downstream.
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| CN108572388A (en) * | 2017-03-07 | 2018-09-25 | 中国辐射防护研究院 | A kind of device and method for the calibration of nuclear facilities liquid effluent γ monitors |
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| CN111290010A (en) * | 2018-12-07 | 2020-06-16 | 中核四0四有限公司 | Device and method for detecting concentration of radioactive airborne effluents |
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