CN103698155A - Comprehensive sampling system for liquid waste treatment system of nuclear power plant - Google Patents
Comprehensive sampling system for liquid waste treatment system of nuclear power plant Download PDFInfo
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- CN103698155A CN103698155A CN201310613081.8A CN201310613081A CN103698155A CN 103698155 A CN103698155 A CN 103698155A CN 201310613081 A CN201310613081 A CN 201310613081A CN 103698155 A CN103698155 A CN 103698155A
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Abstract
The invention relates to a comprehensive sampling system for a liquid waste treatment system of a nuclear power plant. The system includes an in situ sampling box (1), and a sampling pipeline for distillate and heated steam condensate water and a sampling pipeline for condensate liquid, which are connected to the in situ sampling box (1); and a movable type cooler (2) is arranged on the pipeline connecting the sampling pipeline for distillate and heated steam condensate water and the in situ sampling box (1). The invention uses the in situ sampling box as the main body and employs a centralized layout design; and through multi-functionalization of the in situ sampling box, sampling of different liquids under different circumstances can be completed, and cleaning and sweeping can be conducted after the sampling. At the same time, the system can reduce manpower cost required by cleaning, avoid unnecessary contact of the operator with sampling liquid and the sampling box with high radioactive level, so as to protect the operator function.
Description
Technical field
The invention belongs to nuclear power plant's liquid waste disposal technique field, be specifically related to a kind of comprehensive sampling system for nuclear power station liquid waste treatment system.
Background technology
It is the important evidence of judging liquid waste processing effect that nuclear power plant's liquid waste treatment system carries out sample analysis to waste liquid, due to the mode that adopts evaporation and concentration to process, if according to general sampling line design, exist secondary steam condensed fluid to have high temperature risk, and boracic concentrate remains in and easily cause pipeline crystallization in sampling pipe, and because remaining in pipeline, concentrate make sampling there is no representational problem.
Denomination of invention is patented claim on " a kind of water quality automatic analysis sampling system " (application number CN201220175432.2, April 24 2012 applying date), and its disclosed technical scheme is mainly used in the automatic water analysis of pipeline, for be water supply pipe water quality.Denomination of invention is " sampler " (application number CN201130231985.6, July 20 2011 applying date), denomination of invention is " sampler " (application number: CN201130198522.4, June 29 2011 applying date) and denomination of invention be " sampling groove " (application number 201030180952.9, in the technical scheme of Patent Application Publication May 25 2010 applying date), all relate to sampling equipment, can not meet the sampling requirement in nuclear power station liquid waste processing process at all.
Summary of the invention
For the defect existing in prior art; the object of this invention is to provide a kind of comprehensive sampling system for nuclear power station liquid waste treatment system; adopt this comprehensive sampling system to sample on the spot radioactive liquid waste, concentrate, distillate and heating steam condensate water; and can after sampling completes, clean and purge; greatly reduce costs; can avoid sampling liquid and sampling cabinet that operating personnel are higher with radioactive level that unnecessary contacting occurs, protection operating personnel's safety simultaneously.
For reaching above object, the technical solution used in the present invention is: a kind of comprehensive sampling system for nuclear power station liquid waste treatment system, comprise on the spot sampling cabinet and with sampling cabinet is connected on the spot distillate and heating steam condensate water sampling line and concentrate sampling line, distillate and heating steam condensate water sampling line are provided with portable refrigeratory with the pipeline that sampling cabinet is connected on the spot.
Further, be also connected with on the spot sampling cabinet clean-up line on the spot on sampling cabinet, be also connected with sampling line clean-up line on concentrate sampling line, the low-temperature receiver entrance point of portable refrigeratory 2 is connected with distillate and the cooling pipeline of heating steam condensate water; Sampling cabinet clean-up line, sampling line clean-up line and distillate and the cooling pipeline of heating steam condensate water are connected with the demineralized water pipeline of nuclear power plant demineralized water device respectively on the spot.
Further again, on described concentrate sampling line, along being in series with successively on concentrate flow direction, often drive manual isolation valve and sampling line isolation valve; On concentrate sampling line, often open between manual isolation valve and sampling line isolation valve and be connected with concentrate reflux pipeline and pressurized air scavenging line in turn along concentrate flow direction; On concentrate sampling line, the access point of sampling line clean-up line is between the access point and sampling line isolation valve of pressurized air scavenging line.
Further, concentrate sampling line is provided with boron heating device.
Again further, on the pipeline that concentrate reflux pipeline, pressurized air scavenging line and sampling line clean-up line are directly connected with concentrate sampling line, be respectively equipped with boron heating device.
Further, the inlet line of the portable refrigeratory on distillate and heating steam condensate water sampling line is provided with heat insulation structural.
Further, the top of sampling cabinet is connected with nuclear power plant ventilating system by pipeline on the spot, and the bottom of sampling cabinet is connected with hydrophobic gas exhaust duct on the spot.
Further, a side of sampling cabinet is provided with sampling gate on the spot.
Further, the outer portable shielding layer that is arranged with of sampling cabinet on the spot.
The present invention is according to complex situations such as the easy crystallization out of control of boron concentrate in nuclear power station liquid waste treatment system and distillate and condensate temperature height, the sampling cabinet on the spot of take is main body, the design of employing Centralized layout, by making sampling cabinet multifunction on the spot, complete the not sampling of same liquid under different situations, and can after sampling completes, clean and purge, having solved in sampling process is with active sampling line and sampling cabinet to clean and purge, concentrate boron compound crystallisation by cooling out of control, more unmanageable problem in the sampling work such as distillate and heating steam condensate water are cooling, meanwhile, adopt native system to reduce and clean required human cost, prevent that sampling liquid and sampling cabinet that operations staff is higher with radioactive level from unnecessary contacting occurring, thereby play protection operations staff's function.
Accompanying drawing explanation
Fig. 1 is the structural representation of a kind of comprehensive sampling system for nuclear power station liquid waste treatment system provided by the invention.
Embodiment
Below in conjunction with the drawings and specific embodiments, the invention will be further described.
As shown in Figure 1, a kind of comprehensive sampling system for nuclear power station liquid waste treatment system provided by the present invention, comprise on the spot sampling cabinet 1 and with sampling cabinet 1 is connected on the spot distillate and heating steam condensate water sampling line (between node N03 to N05) and concentrate sampling line (between node N08 to N12), distillate and heating steam condensate water sampling line are provided with portable refrigeratory 2 with the pipeline that sampling cabinet 1 is connected on the spot.
In addition, on sampling cabinet 1, be also connected with on the spot sampling cabinet clean-up line (between node N14 to N07) on the spot, for rinsing sampling cabinet 1 on the spot.On concentrate sampling line, be also connected with sampling line clean-up line (between node N06 to N12), for rinsing sampling line.The low-temperature receiver entrance point of portable refrigeratory 2 is connected with distillate and the cooling pipeline of heating steam condensate water (between node N13 to N02).And sampling cabinet clean-up line, sampling line clean-up line and distillate and the cooling pipeline of heating steam condensate water are connected with the demineralized water pipeline (between node N01 to N06) of nuclear power plant's demineralized water device respectively on the spot, to make full use of demineralized water.
In the present invention, the top of sampling cabinet 1 can be connected with nuclear power plant ventilating system by pipeline on the spot, for keeping the negative pressure of sampling cabinet on the spot, contaminated to reduce in room air.The bottom of sampling cabinet 1 is provided with hydrophobic gas exhaust duct on the spot, for draining waste sample liquid and the wash-down water of sampling cabinet on the spot.
For convenience of controlling, sampling cabinet clean-up line is provided with sampling cabinet clean-up line isolation valve 9 on the spot on the spot, distillate and the cooling pipeline of heating steam condensate water are provided with distillate and the cooling pipeline isolation valve 4 of heating steam condensate water, and demineralized water pipeline is provided with brine pipeline non-return valve 3.
On concentrate sampling line, along being in series with successively on concentrate flow direction, often drive manual isolation valve 12 and sampling line isolation valve 11; On concentrate sampling line, often open between manual isolation valve 12 and sampling line isolation valve 11 and be connected with concentrate reflux pipeline (between node N09 to N15) and pressurized air scavenging line (between node N10 to N12) in turn along concentrate flow direction.On concentrate sampling line, the access point of sampling line clean-up line is between the access point and sampling line isolation valve 11 of pressurized air scavenging line.Concentrate sampling line, pressurized air scavenging line and sampling line clean-up line share sampling line isolation valve 11.
Adopt said structure, after concentrate sampling, by concentrate reflux pipeline, concentrate remaining in concentrate sampling line is back in liquid waste treatment system, reduce current sampling for the impact of lower sub-sampling, improve the precision of each concentrate sampling.The pressurized air that accesses public compressed air system by pressurized air scavenging line can purge sampling cabinet on the spot, after purging, gas is discharged by the pipeline being connected with ventilating system arranging on sampling cabinet 1 on the spot.
In addition, concentrate sampling line is provided with boron heating device (as the pipeline of wave molding representative in Fig. 1), boron heating device adopts the form that in pipeline external thermal insulation, electrical heating resistance wire is set to pipeline heating, prevents that concentrate boron compound is out of control cooling and cause crystallization, blocking pipe.Consider concentrate may enter into the pipeline being directly connected with concentrate sampling line and cause crystallization, preferably, on concentrate reflux pipeline on the pipeline between node N09-N15, pressurized air scavenging line on the pipeline between node N11-N16 and sampling line clean-up line the pipeline between node N06-N17 be also respectively equipped with boron heating device.
For convenience of controlling, sampling line clean-up line is provided with sampling line clean-up line isolation valve 10, concentrate reflux pipeline is provided with concentrate reflux pipeline isolation valve 13, and pressurized air scavenging line is provided with pressurized air scavenging line non-return valve 15, pressurized air scavenging line isolation valve 14.
For convenience of controlling, distillate and heating steam condensate water sampling line are provided with distillate and heating steam condensate water sampling line isolation valve 6.For convenience of connecting, on distillate and heating steam condensate water sampling line, be also provided with two distillates and heating steam condensate water sampling line rapid-acting coupling 7,8, distillate and heating steam condensate water sampling line are connected with portable refrigeratory 2 by rapid-acting coupling 7, and portable refrigeratory 2 is connected with sampling cabinet 1 on the spot by rapid-acting coupling 8.Distillate and heating steam condensation flow through distillate and heating steam condensate water sampling line by portable refrigeratory 2, undertaken cooling after, then enter sampling cabinet 1 on the spot and carry out sampling work.
In addition, the inlet line (between node N03 to N04) of the portable refrigeratory 2 on distillate and heating steam condensate water sampling line is provided with heat insulation structural (as the represented pipeline of three lines in Fig. 1), and anti-damage is to operations staff.
For convenience of connecting, on distillate and the cooling pipeline of heating steam condensate water, be also provided with distillate and the cooling pipeline rapid-acting coupling 5 of heating steam condensate water, for being connected with portable refrigeratory 2, the demineralized water of flow through distillate and the cooling pipeline of heating steam condensate water drains into land drain by pipeline after by portable refrigeratory 2.
For convenience of sampling, a side of sampling cabinet 1 can be provided with sampling gate 16 on the spot, extracts the waste liquid of collecting for operations staff.
Consider that concentrate radioactive dosage is higher, the outer portable shielding layer (as shown in phantom in Figure 1) that is arranged with of sampling cabinet 1 on the spot, to protect operating personnel.Portable shielding layer can consist of movable lead.
Above-described embodiment just illustrates of the present invention, and the present invention also can implement with other ad hoc fashion or other particular form, and does not depart from main idea of the present invention or essential characteristic.Therefore, the embodiment of description all should be considered as illustrative but not determinate from the viewpoint of any.Scope of the present invention should illustrate by the claim of adding, and any and the intention of claim and the variation of scope equivalence also should be within the scope of the present invention.
Claims (9)
1. the comprehensive sampling system for nuclear power station liquid waste treatment system, it is characterized in that, described comprehensive sampling system comprise on the spot sampling cabinet (1) and with sampling cabinet (1) is connected on the spot distillate and heating steam condensate water sampling line and concentrate sampling line, distillate and heating steam condensate water sampling line are provided with portable refrigeratory (2) with the pipeline that sampling cabinet (1) is connected on the spot.
2. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 1, it is characterized in that, on sampling cabinet (1), be also connected with sampling cabinet clean-up line on the spot on the spot, on concentrate sampling line, be also connected with sampling line clean-up line, the low-temperature receiver entrance point of portable refrigeratory (2) is connected with distillate and the cooling pipeline of heating steam condensate water; Sampling cabinet clean-up line, sampling line clean-up line and distillate and the cooling pipeline of heating steam condensate water are connected with the demineralized water pipeline of nuclear power plant demineralized water device respectively on the spot.
3. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 2, it is characterized in that, on described concentrate sampling line, along being in series with successively on concentrate flow direction, often drive manual isolation valve (12) and sampling line isolation valve (11); On concentrate sampling line, often open between manual isolation valve (12) and sampling line isolation valve (11) and be connected with concentrate reflux pipeline and pressurized air scavenging line in turn along concentrate flow direction; On concentrate sampling line, the access point of sampling line clean-up line is positioned between the access point and sampling line isolation valve (11) of pressurized air scavenging line.
4. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 3, is characterized in that, concentrate sampling line is provided with boron heating device.
5. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 4, it is characterized in that, on the pipeline that concentrate reflux pipeline, pressurized air scavenging line and sampling line clean-up line are directly connected with concentrate sampling line, be respectively equipped with boron heating device.
6. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 1, is characterized in that, the inlet line of the portable refrigeratory (2) on distillate and heating steam condensate water sampling line is provided with heat insulation structural.
7. according to the arbitrary described a kind of comprehensive sampling system for nuclear power station liquid waste treatment system of claim 1-6, it is characterized in that, the top of sampling cabinet (1) is connected with nuclear power plant ventilating system by pipeline on the spot, and the bottom of sampling cabinet (1) is connected to hydrophobic gas exhaust duct repeatedly on the spot.
8. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 1 and 2, is characterized in that, a side of sampling cabinet (1) is provided with sampling gate (16) on the spot.
9. a kind of comprehensive sampling system for nuclear power station liquid waste treatment system according to claim 1 and 2, is characterized in that, on the spot the outer portable shielding layer that is arranged with of sampling cabinet (1).
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104900283A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A nuclear power plant radioactive liquid waste treatment system |
| CN105510067A (en) * | 2015-12-01 | 2016-04-20 | 中广核工程有限公司 | Comprehensive performance verification method for nuclear power station evaporator |
| CN106017972A (en) * | 2016-06-16 | 2016-10-12 | 南京源自电力自动化设备有限公司 | Automatic sampling device for nuclear island waste resin |
| CN109425501A (en) * | 2017-08-24 | 2019-03-05 | 中广核工程有限公司 | Nuclear power station liquid sampling integration of equipments design method and its equipment |
| CN110223791A (en) * | 2019-04-12 | 2019-09-10 | 中国核动力研究设计院 | A kind of core sampling system that can be used for after pressurized-water reactor nuclear power plant accident |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104900283A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A nuclear power plant radioactive liquid waste treatment system |
| CN105510067A (en) * | 2015-12-01 | 2016-04-20 | 中广核工程有限公司 | Comprehensive performance verification method for nuclear power station evaporator |
| CN105510067B (en) * | 2015-12-01 | 2019-03-19 | 中广核工程有限公司 | The comprehensive performance verification method of nuclear power station vaporising device |
| CN106017972A (en) * | 2016-06-16 | 2016-10-12 | 南京源自电力自动化设备有限公司 | Automatic sampling device for nuclear island waste resin |
| CN106017972B (en) * | 2016-06-16 | 2017-03-29 | 南京源自电力自动化设备有限公司 | Nuclear island spent resin automatic sampling device |
| CN109425501A (en) * | 2017-08-24 | 2019-03-05 | 中广核工程有限公司 | Nuclear power station liquid sampling integration of equipments design method and its equipment |
| CN110223791A (en) * | 2019-04-12 | 2019-09-10 | 中国核动力研究设计院 | A kind of core sampling system that can be used for after pressurized-water reactor nuclear power plant accident |
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| CN103698155B (en) | 2016-04-27 |
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