CN101814326A - Pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment - Google Patents
Pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment Download PDFInfo
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Abstract
The invention relates to pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment, which is characterized in that the equipment mainly consists of a buffer tank (1), a prefilter (2), a drier (3), a heating device (4), a protection bed (5) and at least two delay beds (6) and (7), wherein the protection bed (5) is filled with active carbon, the delay beds (6) and (7) are connected in series, the gas inlet end of the buffer tank (1) is connected with the output end of a groove tank for collecting waste gas through a pipeline, the output end of the buffer tank (1) is connected with the input end of the prefilter (2), the output end of the prefilter (2) is connected with the input end of the drier (3), the output end of the drier (3) is connected with the input end of the heating device (4), the output end of the heating device (4) is connected with the input end of the protection bed (5), the output end of the protection bed (5) is connected with the input end of the delay bed (6), the output end of the delay bed (7) is connected with the input end of an efficient grain filter (8) through a pipeline, and the output end of the efficient grain filter (8) is connected with the corresponding input end of a plant building ventilation system (9). The invention has the advantages of simple structure, ground saving, energy saving, low operation and maintenance cost, safety and reliability.
Description
Technical field
The present invention relates to a kind of nuclear power plant equipment, especially a kind of nuclear power station waste gas treatment equipment, specifically a kind of pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay is processed into covering device.
Background technology
As everyone knows, China's nuclear power cause 20 years of development courses of having passed by, at present, the nuclear power station that enters commercialized running mainly contains: Qinshan first phase, second phase, three phases, Daya Gulf, mountain range Australia first phase, second phase and gulf, field nuclear power station, its nuclear power total amount accounts for 1.9% of national gross generation, and the average nuclear power in the whole world has accounted for 16% of gross generation, and wherein the U.S., Japan, French nuclear power ratio reach 20%, 30%, 80% respectively.China's nuclear power is compared with world average level and there is a big difference.
The development nuclear power is to satisfy Electricity Demand, optimization energy structure, guarantee energy security, promotes the great strategic measure of sustained economic development; Be to reduce environmental pollution, realize the effective way of economy and ecologic environment coordinated development; Be to promote the nuclear industry development, keep and improve the main means of national nuclear deterrent; Be the important measures that promote the equipment manufacture industrial upgrading; The development nuclear power meets the trend that world energy sources utilizes.
China plans 8,000 ten thousand kilowatts of the operations of will going into operation of the year two thousand twenty nuclear power, and the nuclear power of China will account for 4% of gross generation when the time comes, and the nuclear power of approved construction at present has 28 units.
Yet the safe handling of a large amount of radioactive wastes that nuclear power plant produces is one of gordian techniquies of development nuclear power.It is exactly one of factor that directly influences atmosphere safety that height is wherein put waste gas.
Height is put waste gas and mainly is made up of hydrogen, nitrogen and fission gas krypton, xenon.These fission gas radiological doses are very high, and specific activity can reach 10
8～10
9Bq/t accounts for more than 85% of the total specific activity of heap water.If these high radioactivity gases are not handled or dealt with improperly, will be formed internal radiation, the serious threat health of human body by the human body suction, therefore, these height were put waste gas before entering atmosphere, must handle, and made its radioactive level be lower than the environmental emission permissible value.
At present, height is put the principle that treatment of waste gas is all followed " rationally feasible low as far as possible " both at home and abroad.The basic skills of handling is to allow radioactive nuclide in the waste gas, carries out natural decay in setting-up time, makes radioactive dosage be reduced to the permission discharge value.Its method is concluded and mainly contained: pressurization is stored and is handled, and normal temperature activated charcoal retardation is handled.
1) pressurization is stored and is handled
Pressurization is stored and handled is the treatment process that adopts the earliest in the pressurized-water reactor nuclear power plant.Its method is that the height that each tank is discharged is put waste gas, arrives 0.7-0.8MPa with compressor pressurizes.Be stored in a plurality of waste gas delay tanks, stored 40-60 days, make after the radioactive dosage of gas is reduced to emission standard in the delay tank, (HEPA has entering of control to enter atmosphere after the factory building exhaust duct dilutes by highly effective particle filter again.
The processing advantage is stored in pressurization: technical maturity, flow process is simple.Shortcoming is: the processing capacity is big; Pressure storage tank has spillage risk; Compressor operating is safeguarded complicated; Energy resource consumption is big, the operating cost height.The just uncommon agate nuclear power station of Pakistan that Up for Qinshan Nuclear Power Plant of China and Daya Bay Nuclear Power Plant, China help build etc. all adopts pressurization to store disposal route.External early stage nuclear power station also mostly adopts this disposal route.
2) normal temperature acticarbon retardation is handled
It is the new technology that height is put exhaust-gas treatment that normal temperature activated charcoal retardation is handled, promptly utilize activated charcoal that the characteristics of the absorption selected can be arranged under certain condition, when making radgas flow through activated charcoal, its radioactive nuclide is adsorbed and is trapped on the activated charcoal, and a large amount of inactive hydrogen, nitrogen, then pass the charcoal laminar flow and go out, thereby reduce the radioactive level of waste gas and disposal system is simplified greatly.
The major advantage of comparing the processing of normal temperature retardation with pressurization storage disposal route is: only radgass a large amount of in the waste gas is handled, the processing capacity significantly reduces; Do not have compressor, system is more simplified, move more reliably, keep in repair more convenient; Energy resource consumption is low; , gross investment and operating cost reduce; Owing to the delay tank that replaces high-voltage large-capacity with the retardation bed, significantly reduced and leaked the pollution that causes working environment simultaneously.Therefore developing a kind of activated charcoal set treatment device that is applicable to is to reduce the key that the nuclear power station height is put the exhaust-gas treatment cost.
Summary of the invention
The objective of the invention is the shortcoming that the existing nuclear power station height of pin is put that waste gas pressurization process device investment is big, occupation of land is many, maintenance difficulties is big, operating cost is high and the radgas spillage risk is arranged, design a kind of pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay and be processed into covering device based on the charcoal absorption technology.
Technical scheme of the present invention is:
A kind of pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay is processed into covering device; it is characterized in that it is mainly by surge tank 1; prefilter 2; exsiccator 3; well heater 4; the retardation bed 6 of protection bed 5 and at least two serial connections; 7 form; protection bed 5 and retardation bed 6; all be filled with activated charcoal in 7; the inlet end of surge tank 1 links to each other by the output terminal of pipeline with the tank of collecting waste gas; the output terminal of surge tank 1 links to each other with the input end of prefilter 2; the output terminal of prefilter 2 links to each other with the input end of exsiccator 3; the output terminal of exsiccator 3 links to each other with the input end of well heater 4; the output terminal of well heater 4 links to each other with the input end of protection bed 5; the output terminal of protection bed 5 links to each other with the input end of retardation bed 6; the output terminal of retardation bed 7 links to each other by the input end of pipeline with highly effective particle filter 8, and the output terminal of highly effective particle filter 8 links to each other with power house ventilation system 9 corresponding input end.
Described exsiccator 3 is the water-cooled freeze-dryer, and it is by linking to each other with output, the input port of chilled water system 11 into and out of pipeline accordingly.
Described surge tank 1, prefilter 2 and exsiccator 3 all the condensed fluid discharging tube by separately link to each other with liquid waste treatment system 10.
The output terminal of the input end of described surge tank 1, protection bed 5 and the output terminal of each retardation bed all connecting tube by separately link to each other with vacuum sampling system 12 corresponding input end.
Described retardation bed 6,7 is made up of tubular container that is similar to W shape and the acticarbon that is potted in the container.
Beneficial effect of the present invention:
The present invention fills up China and is utilizing the charcoal treatment height to put the blank in this field of waste gas, favourablely catch up with and surpass the world level that the nuclear power height is put exhaust-gas treatment, promote China's nuclear power equipment international competitiveness, ensure that China's nuclear power facility long-term safety effectively moves, and for AP1000 nuclear power station from now in peach blossom river, Hunan, the nuclear power generating sets of Pengze, Jiangxi and follow-up other AP1000, heap types such as CAP1400, CAP1700 provide the radioactive emission disposal plant that meets design requirement to lay a good foundation.
The present invention is simple in structure, and is easily manufactured, and operation, maintenance cost is low, security and reliability height.It is the upgraded product of the high venting of existing pressurization body treatment facility.
Description of drawings
Fig. 1 is the composition structural representation of complete equipment of the present invention.
Embodiment
The present invention is further illustrated below in conjunction with drawings and Examples.
As shown in Figure 1.
A kind of pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay is processed into covering device; it is mainly by surge tank 1; prefilter 2; exsiccator 3; well heater 4; the retardation bed 6 of protection bed 5 and at least two serial connections; 7 form; retardation bed 6; 7 are made up of heavy caliber tubulose container that is similar to W shape and the acticarbon that is potted in the container; adopt W shape (also can adopt S shape; M shapes etc.) structure is in order to prolong the length of retardation bed; it is long as far as possible to make height put the time that waste gas stops in the retardation bed; to improve adsorption effect; as shown in Figure 1; protection bed 5 and retardation bed 6; all be filled with activated charcoal in 7; the inlet end of surge tank 1 links to each other by the output terminal of pipeline with the tank of collecting waste gas; the output terminal of surge tank 1 links to each other with the input end of prefilter 2; the output terminal of prefilter 2 links to each other with the input end of exsiccator 3; exsiccator 3 can adopt the water-cooled freeze-dryer; it is by advancing accordingly; go out the output of pipeline and chilled water system 11; the input port links to each other; the output terminal of exsiccator 3 links to each other with the input end of well heater 4; the output terminal of well heater 4 links to each other with the input end of protection bed 5; the effect of protection bed 5 is when water cut exceeds standard in the contingency air-flow; activated charcoal in the protection bed was lost efficacy; at this moment only need a spot of activated charcoal in the protection bed 5 is carried out activation processing; can reduce operating cost; thereby play effect to the protection of retardation bed; the output terminal of protection bed 5 links to each other with the input end of retardation bed 6; the output terminal of retardation bed 7 links to each other by the input end of pipeline with highly effective particle filter 8, and the output terminal of highly effective particle filter 8 links to each other with power house ventilation system 9 corresponding input end.In order to understand the radiation situation of radioactive grain in the waste gas in real time; the present invention also is provided with a vacuum sampling system 12, and vacuum sampling system 12 links to each other with the input end of corresponding surge tank 1, the output terminal of protection bed 5 and the output terminal of each retardation bed by connecting tube.
The present invention protects the technical indicator of the activated charcoal that uses in bed 5 and the retardation bed 6,7 as shown in the table.
Principle of work of the present invention is:
The waste gas that is come by each tank mixes surge tank 1 in, remove foreign material through prefilter 2 enters and enters well heater 4 heating after exsiccator 3 carries out cooling and dehumidifying to reduce the relative humidity of air-flow, then through protecting beds 5 to enter retardation bed 6,7.Because activated charcoal is selected the effect of absorption in the retardation bed, making in the gas stream inactive hydrogen, nitrogen pass the charcoal laminar flow goes out, and radgas krypton xenon is attracted to and is detained a period of time on the retardation bed, radioactivity level is decay to meet emission level, after HEPA filtrator 8 filters, have entering in the power house ventilation system 9 of control to discharge.
The prior art that maybe can adopt all same as the prior art of grading part that the present invention does not relate to such as each process tank, the employed material of bed, electrical control division is realized.
Claims (5)
1. a pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay is processed into covering device; it is characterized in that it is mainly by surge tank (1); prefilter (2); exsiccator (3); well heater (4); the retardation bed (6 of protection bed (5) and at least two serial connections; 7) form; protection bed (5) and retardation bed (6; 7) all be filled with special-purpose retardation activated charcoal in; the inlet end of surge tank (1) links to each other by the output terminal of pipeline with the tank of collecting waste gas; the output terminal of surge tank (1) links to each other with the input end of prefilter (2); the output terminal of prefilter (2) links to each other with the input end of exsiccator (3); the output terminal of exsiccator (3) links to each other with the input end of well heater (4); the output terminal of well heater (4) links to each other with the input end of protection bed (5); the output terminal of protection bed (5) links to each other with the input end of retardation bed (6); the output terminal of retardation bed (7) links to each other by the input end of pipeline with highly effective particle filter (8), and the output terminal of highly effective particle filter (8) links to each other with power house ventilation system (9) corresponding input end.
2. pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay according to claim 1 is processed into covering device, it is characterized in that described exsiccator (3) is the water-cooled freeze-dryer, it is by linking to each other with output, the input port of chilled water system (11) into and out of pipeline accordingly.
3. pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay according to claim 1 is processed into covering device, it is characterized in that described surge tank (1), prefilter (2) and exsiccator (3) all the condensed fluid discharging tube by separately link to each other with liquid waste treatment system (10).
4. pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay according to claim 1 is processed into covering device, and the output terminal that it is characterized in that the output terminal of input end, protection bed (5) of described surge tank (1) and each the retardation bed all connecting tube by separately links to each other with vacuum sampling system (12) corresponding input end.
5. pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay according to claim 1 is processed into covering device, it is characterized in that described retardation bed (6,7) is made up of tubular container that is similar to W shape and the acticarbon that is potted in the container.
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102226949A (en) * | 2011-04-20 | 2011-10-26 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN102969037A (en) * | 2012-12-11 | 2013-03-13 | 中广核工程有限公司 | Radioactive waste gas treatment system of nuclear power plant |
| CN103474121A (en) * | 2013-09-24 | 2013-12-25 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power plant |
| CN105122376A (en) * | 2013-03-27 | 2015-12-02 | 阿海珐有限公司 | Venting system for the containment structure of a nuclear installation |
| CN105355249A (en) * | 2015-11-16 | 2016-02-24 | 中广核工程有限公司 | Radioactive waste gas processing device for nuclear power station |
| CN106378257A (en) * | 2016-11-17 | 2017-02-08 | 无锡大功机械制造有限公司 | Waste gas conveying dust removing pipe |
| CN108182980A (en) * | 2017-11-27 | 2018-06-19 | 中核控制系统工程有限公司 | It is a kind of to sob the air-channel system for inhaling detection device online suitable for fuel can |
| CN109166641A (en) * | 2018-09-30 | 2019-01-08 | 岭东核电有限公司 | Low-level Spent Radioactive gas processing system in a kind of lead bismuth heap |
| CN112717625A (en) * | 2020-11-23 | 2021-04-30 | 岭东核电有限公司 | Hydrogen-containing waste gas treatment system of nuclear power station |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102226949A (en) * | 2011-04-20 | 2011-10-26 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN102226949B (en) * | 2011-04-20 | 2014-03-19 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN102969037A (en) * | 2012-12-11 | 2013-03-13 | 中广核工程有限公司 | Radioactive waste gas treatment system of nuclear power plant |
| CN102969037B (en) * | 2012-12-11 | 2016-01-13 | 中广核工程有限公司 | Nuclear power station Spent Radioactive gas processing system |
| CN105122376A (en) * | 2013-03-27 | 2015-12-02 | 阿海珐有限公司 | Venting system for the containment structure of a nuclear installation |
| CN103474121A (en) * | 2013-09-24 | 2013-12-25 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power plant |
| CN105355249A (en) * | 2015-11-16 | 2016-02-24 | 中广核工程有限公司 | Radioactive waste gas processing device for nuclear power station |
| CN106378257A (en) * | 2016-11-17 | 2017-02-08 | 无锡大功机械制造有限公司 | Waste gas conveying dust removing pipe |
| CN108182980A (en) * | 2017-11-27 | 2018-06-19 | 中核控制系统工程有限公司 | It is a kind of to sob the air-channel system for inhaling detection device online suitable for fuel can |
| CN109166641A (en) * | 2018-09-30 | 2019-01-08 | 岭东核电有限公司 | Low-level Spent Radioactive gas processing system in a kind of lead bismuth heap |
| CN109166641B (en) * | 2018-09-30 | 2020-09-18 | 岭东核电有限公司 | Low-level radioactive waste gas treatment system in lead bismuth reactor |
| CN112717625A (en) * | 2020-11-23 | 2021-04-30 | 岭东核电有限公司 | Hydrogen-containing waste gas treatment system of nuclear power station |
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Application publication date: 20100825 |