CN204009085U - A kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device - Google Patents
A kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device Download PDFInfo
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- CN204009085U CN204009085U CN201420391610.4U CN201420391610U CN204009085U CN 204009085 U CN204009085 U CN 204009085U CN 201420391610 U CN201420391610 U CN 201420391610U CN 204009085 U CN204009085 U CN 204009085U
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Abstract
The utility model discloses a kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device, this device comprises the measurement chamber (2) being arranged on exhausting waste gas pipeline, the lateral wall of measuring chamber be connected with is respectively communicated with described measurement chamber interior for carry out the radiation detector (3) of radiological measuring to flowing through the hydrogeneous radioactive emission of measurement chamber, and the pressure transducer that pressure is measured (5), this device also comprises the unit of processes and displays on the spot that is connected with radiation detector and is connected with pressure transducer by signal wire (6) by data line (4), processes and displays unit is for the signal of received radiation detector and pressure transducer output on the spot.The utility model provides a kind of nuclear power plant simple in structure, that the response time is short, slip is low, cost is lower, convenient for installation and maintenance, operational reliability is higher hydrogeneous waste gas radioactivity continuous monitoring device.
Description
Technical field
The utility model relates to nuclear power plant's Radiation monitoring technical field, more particularly, relates to a kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device.
Background technology
Nuclear power plant can produce hydrogeneous radioactive emission and discharge in operational process.Hydrogeneous waste gas is mainly the purging exhaust from the normal exhaust of the system equipment that contains reactor coolant and maintenance process generation, and exhaust gas constituents is mainly hydrogen, nitrogen, radioactivity inert gas, iodine etc.Therefore, for to protect mankind environment, reduce public's radiation dose, at present the hydrogeneous waste gas of nuclear power plant's exhaust treatment system before discharge all in delay tank after decay is stored in overcompression, then discharge.Before discharge, first by core sampling system, the hydrogeneous waste gas of discharge is carried out to hand sampling analysis, after radioactive level that analysis result provides is up to standard, provide discharge permit order, and carry out toxic emission in the mandate of master-control room, under monitoring.Simultaneously, the 8.3rd joint regulation in GB GB9136-1988 < < PWR nuclear power plant radioactive emission Processing System Design regulation > > (existing), discharging waste gas radiation monitoring equipment need record and indicate the gas flow of exhaust treatment system bleeder line, activity concentration is recorded, shown and reports to the police, and can when height is reported to the police, automatically stop toxic emission.
Radioactivity continuous monitor table is not all set on the exhaust line of existing unit exhaust treatment system, does not meet GB requirement.Therefore,, in order to reach GB, radioactivity continuous monitor table need to be set on exhaust line.
For the monitoring of waste gas radioactivity, in prior art, on the bleeder line of nuclear power generating sets exhaust treatment system, be provided with sampling continuous monitor and carry out the monitoring of waste gas radioactivity, its principle flow chart is as shown in Fig. 1.Former sampling continuous monitor mainly contains two parts and forms: sampling loop and measurement mechanism.Sampling loop has comprised stopple coupon entrance, measuring chamber, flowmeter, sampling pump, grab simpler and sampling outlet pipe.The workflow of former sampling continuous monitor is as follows: when nuclear power plant carries out toxic emission, the waste gas in bleeder line enters measuring chamber through sampling inlet tube.In measuring chamber, electric impulse signal is detected and be converted in the β ray chamber of being ionized that waste gas is emitted, and this pulse signal is being processed and calculated in processes and displays unit on the spot, obtains the total β level of activity who measures waste gas.Waste gas after measurement is by blowback toxic emission pipeline.Wherein, flowmeter is for reading the gas flow of sampling line.
But there is following defect in the above-mentioned sampling continuous monitor of prior art:
(1) sampling continuous monitor is provided with sampling loop device, and a whole set of monitoring system is complicated, and the size of equipment is larger, and installation and service clearance require larger;
(2) sampling continuous monitor is provided with sampling loop device, and the operation and control of equipment is comparatively complicated, and therefore, failure rate increases, and operational reliability reduces;
(3) monitoring device component devices is many, and tie point is many, makes to leak possibility occurrence and increases;
(4) ionization chamber in monitoring device need to add high pressure, and for hydrogeneous radioactive emission, increases burning or explosion potential, and security is lower.
Utility model content
The technical problems to be solved in the utility model is, the defect existing for the above-mentioned monitoring device equipment of prior art, provides a kind of nuclear power plant simple in structure, that the response time is short, slip is low, cost is lower, convenient for installation and maintenance, operational reliability is higher hydrogeneous waste gas radioactivity continuous monitoring device.
The utility model solves the technical scheme that its technical matters adopts: construct a kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device, comprise be arranged on exhausting waste gas pipeline measurement chamber, the lateral wall of described measurement chamber be connected be respectively communicated with described measurement chamber interior for carry out the radiation detector of radiological measuring to flowing through the hydrogeneous radioactive emission of described measurement chamber, and for carrying out tonometric pressure transducer to flowing through the hydrogeneous radioactive emission of described measurement chamber, this device also comprises the unit of processes and displays on the spot that is connected with described radiation detector and is connected with described pressure transducer by signal wire by data line, described processes and displays on the spot unit is for receiving the signal of described radiation detector and the output of described pressure transducer.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described measurement chamber comprises main paragraph, correspondence is connected to the First Transition section and the second transition section and the first linkage section being fixedly connected with described First Transition section and the second linkage section being fixedly connected with described the second transition section at described main paragraph two ends, described First Transition section and the second transition section are respectively along extending axially and undergauge gradually away from described main paragraph, described the first linkage section with on the second linkage section, be separately installed with web member and be connected with exhausting waste gas pipeline by described web member, described pressure transducer and radiation detector are disposed on respectively on described main paragraph sidewall and with described main paragraph sidewall and are tightly connected.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described main paragraph is provided with the first perforate, in described the first perforate, be welded with for the base of described radiation detector is installed, on described main paragraph, be also provided with the second perforate, in described the second perforate, be welded with for the base of described pressure transducer is installed, wherein, the axis of described the first perforate and the second perforate is respectively perpendicular to the axis of described measurement chamber.
In a kind of nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described radiation detector is plastic scintillator detector.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described radiation detector is cylindrical, comprise detector body, the installation portion being connected with described base and the connecting portion being connected with described data line, in described detector body, be arranged with vertically photomultiplier, described photomultiplier outside is enclosed with permalloy tape.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described installation portion part has been disposed radially photoconduction glass, on the end face of described photoconduction glass near measurement chamber, by crimping mode, be fixed with plastic scintillant, described plastic scintillant is paved with the end face of described photoconduction glass.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, described plastic scintillant and the processing of described photoconduction bulk glass, and from the first perforate, extend to and measure in chamber after installation.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, on the cabinet of described processes and displays on the spot unit, be provided with the normal green indicating lamp of system, one-level superthreshold yellow alarm pilot lamp, secondary superthreshold red alarm pilot lamp, system exception yellow indicator lamp and alarm buzzer.
In nuclear power plant described in the utility model hydrogeneous waste gas radioactivity continuous monitoring device, the tested pipeline section periphery of described radiation detector and hydrogeneous radioactive emission delivery pipe is provided with lead shield body.
Implement a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device, there is following beneficial effect: due to measurement chamber is directly installed on exhausting waste gas pipeline, and radiation detector and pressure transducer are arranged on measurement chamber, adopt plastic scintillator detector, and at the outside of photomultiplier parcel permalloy tape, put up with that to process power module and the data processing module of display unit integrated simultaneously, make this monitoring device there is following features: the operation of (1) this monitoring device system requires simple with control, failure rate is low, can guarantee its security of operation and reliable, (2) the withstand voltage and favorable sealing property of this monitoring device, entity isolated high-voltage power supply and inflammable and explosive waste gas, eliminate risk inflammable and blast, improves the security performance of monitoring device, (3) this monitoring device is simple in structure, installing space is little, is convenient to maintenance of equipment and replacing, reduces maintain and repair methods cost, (4) photomultiplier of this monitoring device outside parcel permalloy tape, reduces outside electromagnetic interference, improves the antijamming capability of monitoring device, (5) this monitoring device has been installed flame-proof type radiation detector, and measurement data is revised, and has improved accuracy of measurement, (6) useful detection area of this monitoring device is adjustable, can realize detector measurement range ability and regulate, (7) casing of the unit of processes and displays on the spot of this monitoring device is equipped with normal run indicator and malfunction indicator lamp, can judge fast the running status of monitoring device in operational process, (8) unit of processes and displays on the spot of this monitoring device becomes one power module and data processing module, omits traditional terminal box design, and device is more simplified.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the utility model is described in further detail, in accompanying drawing:
Fig. 1 is the principle flow chart that the sampling continuous monitor of prior art carries out the monitoring of waste gas radioactivity;
Fig. 2 is the structural representation of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 3 is the cut-open view of the radiation detector of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 4 is the partial enlarged drawing of the first embodiment of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 5 is the cut-open view of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 6 is the partial enlarged drawing in I region in Fig. 5;
Fig. 7 is the partial enlarged drawing of the second embodiment of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 8 is the front view of the unit of processes and displays on the spot of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Fig. 9 is the perspective view of the unit of processes and displays on the spot of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device;
Figure 10 is the measuring principle process flow diagram of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device.
Embodiment
In order to solve existing monitoring device complex structure in prior art, installation and maintenance difficulty, failure rate is high, easily leak, the problems such as operational reliability is low, the utility model main innovate point is: a kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device is provided, this device is for monitoring continuously the beta activity activity of exhaust treatment system discharging waste gas, adopt detection mode in online pipeline to measure, this metering system has saved loop apparatus of the prior art, make monitoring device equipment simpler, being conducive to post facility safeguards and changes, reduce maintenance of equipment cost.When the μ Gy/h of environmental exact details≤10, do not need extra lead shield can meet monitoring requirement.Owing to adopting the plastic scintillator detector of high β/γ ratio, Beta-ray detection efficiency and measuring accuracy have been improved, the risk of the hydrogeneous waste gas blast that can avoid detector to add high pressure causing.Measurement data can be connected with the data network of nuclear power plant, the robotization of detection process and the networking of measurement data have been realized, processes and displays unit can be realized parts power supplies and process on the spot, shows detection data on the spot, has alleviated the burden of centralized control system, makes whole system design more reasonable.
For technical characterictic of the present utility model, object and effect being had more clearly, understand, now contrast accompanying drawing and describe embodiment of the present utility model in detail.
As shown in Figure 2, the utility model provides a kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device, comprise and measure chamber 2, radiation detector 3, pressure transducer 5, wherein, measuring chamber 2 can process separately, the two ends of measuring chamber 2 are connected with bleeder line by web member, and web member can be flange 1, measure chamber 2 and are arranged on hydrogeneous radioactive emission bleeder line.Measure chamber 2 and also can be connected with bleeder line by other connected mode, as long as can accomplish, be tightly connected.This monitoring device has saved sampling loop device of the prior art, and therefore, the space that structure is simpler, installation needs is less.In addition, in the maintenance of equipment in later stage, when changing, can directly monitoring device be removed from exhaust line, convenient and reduced maintain and repair methods cost, also reduced failure rate simultaneously, improved operational reliability.
Measure chamber 2 and comprise main paragraph 201, correspondence is connected to the First Transition section 202 and the second transition section 203 and the first linkage section 204 being fixedly connected with First Transition section 202 and the second linkage section 205 being fixedly connected with described the second transition section 203 at main paragraph 201 two ends, First Transition section 202 and the second transition section 203 are respectively along extending axially and undergauge gradually away from main paragraph 201, the first linkage section 204 with on the second linkage section 205, be separately installed with flange 1 and be connected with exhausting waste gas pipeline by flange 1, pressure transducer 5 and radiation detector 3 are disposed on respectively on main paragraph 201 sidewalls and with main paragraph 201 sidewalls and are tightly connected.Be understandable that, measuring chamber 2 can be also some other parts small in the end and big in the middle.The diameter of main paragraph 201 is maximum, in order to enable to hold enough radgass on the one hand, flow through in order to give buffering of gas of measuring chamber 2 on the other hand, make radgas in relatively static state, with the measurement that is beneficial to radiation detector 3 and pressure transducer 5, make the precision of measurement higher simultaneously.Wherein, the angle between radiation detector 3 and the axis of pressure transducer 5 be 30 degree to 150 degree, optimum is 90 degree, 90 degree arrange radiation detector 3 and pressure transducer 5 can make monitoring device seem more attractive in appearance, and can phase mutual interference when monitoring.
Radiation detector 3 is arranged on to be measured on chamber 2, and the hydrogeneous radioactive emission of measuring chamber 2 to flowing through carries out radioactivity monitoring.Pressure transducer 5 is also arranged on to be measured on chamber 2, and it can be arbitrarily angled with radiation detector 3 formation, but for easy for installation, radiation detector 3 and the pressure transducer 5 of the present embodiment are vertically set on same xsect.Pressure transducer 5 is measured for measure the hydrogeneous Spent Radioactive atmospheric pressure of chamber 2 to flowing through, and by the measurement result of force value correction radiation detector 3, by processing unit 7 on the spot, provides the radioactive concentration of emission gases under normal pressure condition.
Further, the main paragraph 201 of measuring chamber 2 is provided with the first perforate, in the first perforate, be welded with flange seat 8, radiation detector 3 is arranged on flange seat 8 by bolt, on main paragraph 201, be also provided with second perforate vertical with the first perforate, in the second perforate, be welded with base 9, pressure transducer 5 is arranged on base 9.Wherein, the diameter of the first perforate is determined according to the diameter of radiation detector 3, and the diameter of the second perforate is determined by the diameter of pressure transducer 5.The present embodiment radiation detector 3 is vertical with the central axis of measuring chamber 2 respectively with the central axis of pressure transducer 5, the data that make to measure are to belong to the gas of measuring a certain fixed position of chamber, can be because of to measure the gaseous radioactivity activity of chamber diverse location and pressure different and cause measurement result not with reference to property, be above-mentionedly arranged so that measurement result is more accurate.
As shown in Figure 3, the utility model provides a kind of radiation detector, and radiation detector 3 is cylindrical, comprises detector body 301, the installation portion 302 being connected with described flange seat 8 and the connecting portion 303 being connected with data line 4.The radiation detector 3 of the present embodiment has adopted the plastic scintillator detector of high β/γ ratio, thereby has improved detection efficiency and measuring accuracy, and plastic scintillator detector can be polystyrene-p-terphenyl plastic scintillation detectors.
Wherein, detector body 301 comprises stainless steel urceolus 10, is set in the photomultiplier 12 in stainless steel urceolus 10.Further, as shown in Figure 4, at photomultiplier 12 outside parcel permalloy tapes 11, permalloy is a kind of at the iron-nickel alloy compared with there being higher magnetic permeability under low-intensity magnetic field, and permalloy tape 11 can anti-electromagnetic interference (EMI).
Referring to Fig. 4, in the radially outstanding hole forming, stainless steel gland 18 is installed between stainless steel urceolus 10 and flange seat 8, stainless steel gland 18 connects together by stainless steel screw and stainless steel urceolus 10, and on the end face between stainless steel gland 18 and flange seat 8, install O type ring recess additional, be mainly used in sealing.In the centre of stainless steel gland 18, be provided with perforate 14, the diameter of perforate 14 is adjustable, and the area of perforate 14 is the useful detection area of plastic scintillant 16, by regulating the diameter of perforate 14, can change the useful detection area of plastic scintillant 16, thus the detectable lower limit of modifier.
In addition, in the radially outstanding hole forming, plastic scintillant 16 is installed between stainless steel urceolus 10 and stainless steel gland 18, plastic scintillant 16 specifications are the p-terphenyl plastic scintillant 16 that polystyrene is matrix of take of Φ 50mm * 0.5mm, at plastic scintillant 16, by crimping mode, be fixed with the photoconduction glass 15 of high printing opacity near an end face of stainless steel gland 18, the specification of photoconduction glass 15 is Φ 50mm * 10mm, side is evenly coated with reflectorized material, at plastic scintillant 16 test surfaces, be enclosed with the polyester aluminium film of thickness≤12 μ m, waterproof.On an end face at stainless steel gland 18 near photoconduction glass 15, install O type rubber ring 17 additional, O type rubber ring 17 seals.On the end face contacting with photoconduction glass 15 at stainless steel urceolus 10, add ethylene-propylene-diene monomer glue gasket 13, can prevent that photoconduction glass 15 is extruded damage, also can seal.
Above, mention, radiation detector 3 is arranged on and is measured on chamber 2, referring to Fig. 5 by flange seat 8.The partial enlarged drawing in I region in Fig. 5 as shown in Figure 6, on the end face that is connected with stainless steel screw between radiation detector 3 and flange seat 8, add flange seat pad 20, flange seat pad 20 mainly seals, flange seat 8 lower ends are provided with step, between the end face of radiation detector 3 and flange seat 8 lower end steps, install O type circle 19 additional, O type circle 19 mainly seals.Radiation detector 3 to measuring on chamber 2, makes installation and maintenance convenient as an integral installation.
As shown in Figure 7, be the structural representation of installation portion of the radiation detector of the utility model the second embodiment.Referring to Fig. 7, for reducing the detection limit of the utility model monitoring device, by plastic scintillant 16 and the whole processing of photoconduction glass 15, and according to Fig. 7, radiation detector 3 is installed, being about to plastic scintillant 16 inserts and measures in chamber 2 with the integral body of photoconduction glass 15, detection area that like this can Enhanced Radiation Reduced Blast detector 3, reduces the detection limit of the utility model monitoring device.
Further; monitoring device also comprises processes and displays unit 7 on the spot; processes and displays unit 7 is connected with pressure sensor signal line 6 by data line 4 respectively with pressure transducer 5 with radiation detector 3 on the spot; the electric impulse signal of 7 pairs of processes and displays unit radiation detector, 3 outputs receives and processes on the spot; and pressure transducer 5 output signals are received and processed; it is prior art that concrete signal is processed, and is not key protection point of the present invention.Simultaneously also for radiation detector 3 and pressure transducer 5 provide power supply, in addition, processes and displays unit 7 is also responsible for the data of processing to be delivered to external unit on the spot, output data comprise the data of indicating total β volume activity level, external unit can be computer or other display equipment, measurement of correlation data can be connected with the data network of nuclear power plant, have realized the robotization of detection process and the networking of measurement data.The unit of processes and displays on the spot of this monitoring device becomes one power module and data processing module, omits traditional terminal box design, and device is more simplified.
As shown in Figure 8, be the front view of the unit of processes and displays on the spot of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device.Referring to Fig. 8; above the cabinet of processes and displays unit 7 on the spot, one-level superthreshold yellow alarm pilot lamp 21 and secondary superthreshold red alarm pilot lamp 27 are installed, the front that is positioned at cabinet is just provided with the normal green indicating lamp 22 of system, system exception yellow indicator lamp 23 and alarm buzzer 26 on the upper side.
Central authorities in cabinet front are provided with liquid crystal display 25, and for showing output detections result, staff is the beta activity activity situation of change of hydrogeneous waste gas in liquid crystal display 25 is found out current exhausting waste gas pipeline intuitively.In order better display 25 to be operated, below display 25, be provided with operation keyboard 24.
As shown in Figure 9, be the perspective view of the unit of processes and displays on the spot of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device.Referring to Fig. 9, below processes and displays unit 7 cabinets on the spot, signal input output interface 28 is installed, in the present embodiment, signal input output interface 28 comprises four signal input interface and signal output interfaces side by side, wherein, signal input interface can be used for connecing data line 4 and pressure sensor signal line 6, thereby realize being connected of processes and displays unit 7 and radiation detector 3 and pressure transducer 5 on the spot, signal output interface is processed display unit 7 data for putting up with export external unit to, facilitate the later stage check and further analyze.On the side of signal input output interface 28, be also provided with waterproof power switch 30 and Insurance Block 29.
In the cabinet of processes and displays unit 7 on the spot, there are low-voltage power circuit plate 33 and high-voltage power circuit plate 34, and central control circuit plate 31, and by metal partion (metp) 32, low-voltage power circuit plate 33, high-voltage power circuit plate 34 are separated with central control circuit plate 31, can prevent power circuit and the mutual interference of control circuit phase.Wherein, high-voltage power circuit plate 34 provides high-voltage power supply for radiation detector 3, and low-voltage power circuit plate 33 provides required power supply for detector 3, central control circuit plate 31 etc., and central control circuit plate 31 is for data acquisition, data processing and data storage etc.
If Figure 10 is the measuring principle process flow diagram of a kind of nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device.Referring to Figure 10, the workflow of the utility model monitoring device is as follows: in measuring chamber 2, have gas flow out-of-date, after receiving β ray, the plastic scintillant 16 of radiation detector 3 sends fluorescence, through photomultiplier 12, be converted to electric signal, through data line 4, be sent to processes and displays unit 7 on the spot, pressure transducer 5 is measured the pressure that flows through the gas of measuring chamber 2, and by signal wire, pressure signal is sent to processes and displays unit 7 on the spot, processes and displays unit 7 is processed after receiving the signal of radiation detector 3 and pressure transducer 5 on the spot, measurement data to radiation detector 3 is revised, calculate the radioactivity value of the discharging waste gas under normal pressure, and compare with alarm threshold value, when the radioactivity value of gas during lower than alarm threshold value normal pilot lamp bright, when radioactivity value surpasses the flicker of alarm threshold value alarm pilot lamp.And the radioactivity value of the discharging waste gas under normal pressure is delivered to external unit.
Embodiment of the present utility model, except the activity measurement for the hydrogeneous waste gas of nuclear power plant, also can be applicable to similar nuclear facilities or other measurements that contains flammable explosive gas gas in pipelines radioactivity.When the μ Gy/h of environmental exact details≤10, do not need extra shielding can meet monitoring requirement; When environmental exact details > 10 μ Gy/h, can take the mode that increases lead shield at detector outward to realize measurement object.
In sum, nuclear power plant of the present utility model hydrogeneous waste gas radioactivity continuous monitoring device, can realize the functional requirement of sampling continuous monitor of the prior art completely, and the utility model monitoring device adopts detection mode in online pipeline to measure, this metering system has saved loop apparatus of the prior art, make monitoring device equipment simpler, be conducive to post facility and safeguard and change, reduce maintenance of equipment cost.When the μ Gy/h of environmental exact details≤10, do not need extra lead shield can meet monitoring requirement.Owing to having adopted the plastic scintillator detector of high β/γ ratio, thereby improved detection efficiency and measuring accuracy, and the risk of the hydrogeneous waste gas blast of having avoided detector to add high pressure causing.Measurement of correlation data can be connected with the data network of nuclear power plant, the robotization of detection process and the networking of measurement data have been realized, processes and displays unit can be realized parts power supply and process on the spot, shows detection data on the spot, alleviate the burden of centralized control system, made whole system design more reasonable.
By reference to the accompanying drawings embodiment of the present utility model is described above; but the utility model is not limited to above-mentioned embodiment; above-mentioned embodiment is only schematic; rather than restrictive; those of ordinary skill in the art is under enlightenment of the present utility model; not departing from the scope situation that the utility model aim and claim protect, also can make a lot of forms, within these all belong to protection of the present utility model.
Claims (9)
1.Yi Zhong nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device, it is characterized in that, comprise the measurement chamber (2) being arranged on exhausting waste gas pipeline, the lateral wall of described measurement chamber (2) be connected with respectively with described measurement chamber (2) internal communication for carry out the radiation detector (3) of radiological measuring to flowing through the hydrogeneous radioactive emission of described measurement chamber (2), and for carrying out tonometric pressure transducer (5) to flowing through the hydrogeneous radioactive emission of described measurement chamber (2), described device also comprises the unit of processes and displays on the spot (7) that is connected with described radiation detector (3) by data line (4) and is connected with described pressure transducer (5) by signal wire (6), described processes and displays on the spot unit (7) is for receiving the signal of described radiation detector (3) and described pressure transducer (5) output.
2. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 1 continuous monitoring device, it is characterized in that, described measurement chamber (2) comprises main paragraph (201), correspondence is connected to the First Transition section (202) and the second transition section (203) and the first linkage section (204) being fixedly connected with described First Transition section (202) and the second linkage section (205) being fixedly connected with described the second transition section (203) at described main paragraph (201) two ends, described First Transition section (202) and the second transition section (203) are respectively along extending axially and undergauge gradually away from described main paragraph (201), described the first linkage section (204) with on the second linkage section (205), be separately installed with web member and be connected with exhausting waste gas pipeline by described web member, described pressure transducer (5) and radiation detector (3) are disposed on respectively on described main paragraph (201) sidewall and with described main paragraph (201) sidewall and are tightly connected.
3. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 2 continuous monitoring device, it is characterized in that, described main paragraph (201) is provided with the first perforate, in described the first perforate, be welded with for the base of described radiation detector (3) is installed, described main paragraph is also provided with the second perforate on (201), in described the second perforate, be welded with the base (9) for described pressure transducer (5) are installed, wherein, the axis of described the first perforate and the second perforate is respectively perpendicular to the axis of described measurement chamber (2).
4. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 3 continuous monitoring device, is characterized in that, described radiation detector (3) is plastic scintillator detector.
5. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 4 continuous monitoring device, it is characterized in that, described radiation detector (3) comprises detector body (301), the installation portion (302) being connected with described base and the connecting portion (303) being connected with described data line (4);
In described detector body (301), be arranged with vertically photomultiplier (12), described photomultiplier (12) outside is enclosed with permalloy tape (11).
6. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 5 continuous monitoring device, it is characterized in that, described installation portion (302) part has been disposed radially photoconduction glass (15), on the end face of described photoconduction glass (15) near measurement chamber (2), by crimping mode, be fixed with plastic scintillant (16), described plastic scintillant (16) is paved with the end face of described photoconduction glass (15).
7. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 6 continuous monitoring device, it is characterized in that, described plastic scintillant (16) is one-body molded with described photoconduction glass (15), and from the first perforate, extends to and measure in chamber (2) after installation.
8. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 1 continuous monitoring device; it is characterized in that, on described processes and displays on the spot unit (7), be provided with the normal green indicating lamp of system (22), one-level superthreshold yellow alarm pilot lamp (21), secondary superthreshold red alarm pilot lamp (27), system exception yellow indicator lamp (23) and alarm buzzer (26).
9. the hydrogeneous waste gas radioactivity of nuclear power plant according to claim 8 continuous monitoring device, is characterized in that, the tested pipeline section periphery of described radiation detector (3) and hydrogeneous radioactive emission delivery pipe is provided with lead shield body.
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|---|---|---|---|---|
| CN105068110A (en) * | 2015-08-27 | 2015-11-18 | 广东恒聚医疗科技有限公司 | Novel beam detector |
| CN105068110B (en) * | 2015-08-27 | 2018-04-13 | 广东恒聚医疗科技有限公司 | A kind of new beam detector |
| CN106526777A (en) * | 2016-12-23 | 2017-03-22 | 上海奥星制药技术装备有限公司 | NA (Numerical Aperture) connector type sight mirror |
| CN107195342A (en) * | 2017-04-05 | 2017-09-22 | 中广核研究院有限公司 | A kind of method for measuring nuclear power plant's nucleic activity distribution |
| CN107195342B (en) * | 2017-04-05 | 2019-07-30 | 中广核研究院有限公司 | A method of measurement nuclear power plant's nucleic activity distribution |
| CN109991646A (en) * | 2017-12-31 | 2019-07-09 | 中国人民解放军63653部队 | Si-PINX ray detector measures radgas measuring chamber |
| CN109991646B (en) * | 2017-12-31 | 2021-05-28 | 中国人民解放军63653部队 | Measuring chamber for measuring radioactive gas by Si-PINX ray detector |
| CN109001377A (en) * | 2018-06-22 | 2018-12-14 | 佛山瀚兽环境科技服务有限公司 | With the waste gas monitoring device that operating state function is presented |
| CN110308474A (en) * | 2019-07-02 | 2019-10-08 | 中国原子能科学研究院 | A kind of small-sized monitoring device for on-line measurement gas uranium abundance |
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Effective date of registration: 20150924 Address after: 518000, building 2, Tian An digital Pioneer Park, 441 Longcheng street, Longgang District, Guangdong, Shenzhen Patentee after: Shenzhen China Nuclear Power Design Co., Ltd. Patentee after: Beijing rizhiyang technology and trade limited liability company Patentee after: SUNWISE (Beijing) Instrument Manufacturing Co Ltd Address before: Futian District Shenzhen City, Guangdong province 518023 Shennan Road No. 69 Patentee before: China Nuclear Power Engineering Co., Ltd. Patentee before: China General Nuclear Power Corporation |