CN104867528A - Treatment method of process wastewater in nuclear power plant - Google Patents
Treatment method of process wastewater in nuclear power plant Download PDFInfo
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- CN104867528A CN104867528A CN201510148222.2A CN201510148222A CN104867528A CN 104867528 A CN104867528 A CN 104867528A CN 201510148222 A CN201510148222 A CN 201510148222A CN 104867528 A CN104867528 A CN 104867528A
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- CN
- China
- Prior art keywords
- power plant
- nuclear power
- waste water
- technique waste
- treatment method
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/10—Processing by flocculation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
Abstract
The invention relates to a treatment method of radioactive wastewater, and solves the problem that in a conventional treatment method of process wastewater in a nuclear power plant is large in secondary waste quantity, high in energy consumption and the like. The invention provides a treatment method of process wastewater in a nuclear power plant. The treatment method comprises the following steps: (1) chemical flocculants are added in process wastewater, and colloidal radionuclides are flocculated; (2) the process wastewater after being treated in the step (1) passes through an active carbon layer, colloidal radionuclide floccules are filtered out, and most of non-colloidal radionuclides are removed through adsorption; then the process wastewater passes through a zeolite layer to be adsorbed to further remove rest of radionuclides; (3) the process wastewater after being treated in the step (2) is subjected to ion exchange to remove salt and achieve pH regulation. The treatment method minimizes the use amount of ion exchange resin, reduces the secondary waste quantity remarkably, eliminates an evaporation process, reduces the energy consumption greatly, and has better economy.
Description
Technical field
The present invention relates to a kind of disposal route of radioactive wastewater, particularly the disposal route of a kind of nuclear power plant technique waste water.
Background technology
Nuclear power plant's technique waste water mainly comprises three parts, and be respectively the hydrophobic and technique waste water containing high suspended matter particle in the reactor coolant loop effluent of boracic, ground, its radioactive level is generally 10
4~ 10
6bq/L, comprises miscellaneous radioactive nuclide usually.According to the national standard (GB6249-2011) of new revision, the radioactive nuclide of Coastal Nuclear Power Plant's Site slot type floss hole is restricted to 1000Bq/L (tritium and carbon 14 except), and the discharge in factory site, inland is restricted to 100Bq/L.Therefore, need to carry out appropriate process to nuclear power plant's technique waste water, remove radioactive nuclide wherein, to meet emission request.
Except above-mentioned Compulsory Feature, in Radwastes treatment field, treatment of wastes produced also should realize with final disposal being the principle such as " waste minimization " and " optimization of radiation protection " instructed.Wherein, " waste minimization " is significant in the utilization of resources, environmental protection and economy.
The technique waste water process of existing nuclear power plant mainly adopts " filtration+evaporation+ion-exchange " tupe, and this pattern exists many-side and is difficult to overcome the deficiency.
One, secondary refuse amount is large, does not meet " waste minimization " principle.
In this tupe, radioactive nuclide is removed mainly through ion-exchange.Although operation is very easy for ion-exchange treatment, the waste water after process can meet emission request, and a large amount of radioactive spent resins produced are organism, be difficult to better realize solidification process with current technology, therefore secondary refuse amount is large, and geological disposal costly, has greater environmental impacts.
For this reason, this area attempts the radioactive nuclide inorganic adsorbent that exploitation is suitable for, to solve the difficult problem of solidification process.For ferrocyanide adsorbent, this adsorbent is to radioactive nuclide
137cs has very high selectivity,
137the Sorption ratio of Cs is up to 10
5ml/g, but the non-constant of the adsorption effect of this adsorbent to other radioactive nuclides, therefore encounter difficulty when the liquid waste processing of reality.Also there is same problem in other radioactive nuclide inorganic adsorbent.
Its two, energy consumption is large, and economy is poor.
In this tupe, subtract appearance for what realize waste liquid, need to carry out evaporation process to a large amount of technique waste waters, required energy consumption is considerable.
Its three, it is more that this tupe feature inherently also determines required process equipment, complex interfaces, but technique waste water treatment capacity is less, and (representative value is 2 ~ 3m
3/ h).
Its four, owing to have employed evaporation operation, be therefore not suitable for the process containing volatile radioactive nuclide technique waste water; And the pattern of " evaporation+ion-exchange " is also unsuitable for the process of the technique waste water of foam easy to foaming, easily cause the remarkable decline of ion exchange resin exchange capacity.
Summary of the invention
Contain the problems such as the waste water of volatile nuclide and foam easy to foaming for the secondary refuse amount solving the technique waste water process existence of existing nuclear power plant is large, energy consumption is large, process equipment is more, complex interfaces, wastewater treatment capacity are little, be not suitable for process, the invention provides the disposal route of a kind of nuclear power plant technique waste water.
The method comprises the steps:
(1) in nuclear power plant's technique waste water, add chemical floc, colloidal attitude radioactive nuclide is flocculated;
(2) the nuclear power plant's technique waste water after step () being processed passes through active carbon layer, the colloidal attitude radioactive nuclide flocculate generated in filtering step (), and the non-colloidal attitude radioactive nuclide of Adsorption major part; Then, adsorbed by zeolite layer, remove remaining radioactive nuclide further;
(3) the nuclear power plant's technique waste water after step (two) being processed by ion-exchange treatment, realizes pH regulate with desalination.
Can also reverse osmosis step be comprised after the process method step (three) of above-mentioned nuclear power plant technique waste water, thus realize the removal or concentrated of boron.
The amount ratio of described activated charcoal and zeolite is preferably 1:3-1:2 (weight ratio).
The specific surface area of described activated charcoal is preferably 3000m
2/ more than g.
The specific surface area of described zeolite is preferably 600m
2/ more than g.
First disposal route of the present invention flocculates to nuclear power plant's technique waste water, then active carbon layer is passed through, because activated charcoal had both had good filter effect, also good adsorptive power is had, the radioactive nuclide of the wherein overwhelming majority can be adsorbed, there is excellent universality, therefore better achieve the removal of colloidal attitude radioactive nuclide flocculate and most of non-colloidal attitude radioactive nuclide.Meanwhile, filtering colloidal attitude radioactive nuclide flocculate prevents it to the negative effect of follow-up zeolite adsorption and ion-exchange treatment.
Then, by the nuclear power plant's technique waste water through aforementioned processing by zeolite layer, remaining radioactive nuclide is removed.Due to
137cs and
90the primary radionuclides of Sr normally in nuclear power plant's technique waste water, content is relatively high, therefore after charcoal absorption, also has a small amount of existence, and it is right therefore to present invention employs
137cs and
90the zeolite that Sr has good adsorbent performance adsorbs further, obtains good removal effect.Certainly, if also there is other radioactive nuclide of trace, zeolite also can realize absorption preferably to it.
In addition, nuclear power plant also needs to be carried out by technique waste water recycling to realize " waste minimization " usually, at this moment the emission ratio activity of recirculated water is not only needed to meet related request, also require that its conductivity is less than 70 μ S/cm, pH also should meet related request, therefore needs to carry out desalination by ion-exchange treatment and regulate pH; Ion-exchange treatment also can continue to remove the trace radionuclidic existed simultaneously.Sometimes in order to utilization and recycle boron, also need to carry out counter-infiltration except boron or concentrated boron.
For realizing " waste minimization ", the present invention is also studied the amount ratio of activated charcoal and zeolite in whole technique, finds that best weight ratio is 1:3-1:2.
The disposal route of nuclear power plant of the present invention technique waste water is owing to have employed the process route of flocculation, activated carbon filtration and absorption, zeolite adsorption, ion-exchange treatment, farthest decrease the consumption of ion exchange resin, significantly reduce secondary refuse amount, wastewater treatment capacity is unrestricted, is convenient to the technique waste water processing foam easy to foaming; Avoid the employing of evaporation process, greatly reduce energy consumption, there is good economy, and be applicable to the process containing volatile nuclide technique waste water; Processes and apparatus is comparatively simple, and floor area is little, easy to operate, and the common nuclear power plant technique waste water after treatment total specific activity of its radioactivity is less than 50Bq/L, better meets the requirement of directly discharge.At present, the disposal route of nuclear power plant of the present invention technique waste water have passed the radioactive heat checking of process scale.
Embodiment
Below by embodiment, embodiments of the present invention are described further.
Embodiment
A disposal route for nuclear power plant's technique waste water, comprises the steps:
(1) at flow be 360L/h nuclear power plant's technique waste water in add chemical floc, colloidal attitude radioactive nuclide is flocculated.After testing, the radioactive nuclide source item of described nuclear power plant technique waste water comprises 10
4bq/L's
137cs, 10
4bq/L's
90sr, 10
3bq/L's
60co, 10
2bq/L's
110ag and 10
2bq/L's
54fe.
(2) the nuclear power plant's technique waste water after step () being processed passes through active carbon layer, the colloidal attitude radioactive nuclide flocculate generated in filtering step (), and the non-colloidal attitude radioactive nuclide of Adsorption major part; Then, adsorbed by zeolite layer, remove remaining radioactive nuclide further.Through step (two) process after, the radioactive nuclide in technique waste water and specific activity as follows: 12Bq/L's
137cs, 6Bq/L's
90sr, 1Bq/L's
60co,
110ag does not detect, 10
2bq/L's
54fe, decontamination factor is respectively:
137cs is greater than 10000,
90sr is greater than 1000,
60co is greater than 1000,
54fe is greater than 100.
(3) the nuclear power plant's technique waste water after step (two) being processed by ion-exchange treatment, realizes pH regulate with desalination.Through step (three) process after, the radioactive nuclide in technique waste water and specific activity as follows: 1.85Bq/L's
137cs, 0.027Bq/L's
90sr, 0.497Bq/L's
60co, decontamination factor is respectively:
137cs is greater than 10000,
90sr is greater than 1000,
60co is greater than 1000.
(4) counter-infiltration is adopted to remove boron.After step (four) process, boron concentration drops to 100ppm by 500ppm.
Claims (5)
1. a disposal route for nuclear power plant's technique waste water, is characterized in that the method comprises the steps:
(1) in nuclear power plant's technique waste water, add chemical floc, colloidal attitude radioactive nuclide is flocculated;
(2) the nuclear power plant's technique waste water after step () being processed passes through active carbon layer, the colloidal attitude radioactive nuclide flocculate generated in filtering step (), and the non-colloidal attitude radioactive nuclide of Adsorption major part; Then, adsorbed by zeolite layer, remove remaining radioactive nuclide further;
(3) the nuclear power plant's technique waste water after step (two) being processed by ion-exchange treatment, realizes pH regulate with desalination.
2. the disposal route of nuclear power plant as claimed in claim 1 technique waste water, is characterized in that: also comprise reverse osmosis step after step (three), thus realizes the removal or concentrated of boron.
3. the disposal route of nuclear power plant as claimed in claim 1 or 2 technique waste water, is characterized in that: the amount ratio of described activated charcoal and zeolite is 1:3-1:2 (weight ratio).
4. the disposal route of nuclear power plant as claimed in claim 1 or 2 technique waste water, is characterized in that: the specific surface area of described activated charcoal is 3000m
2/ more than g.
5. the disposal route of nuclear power plant as claimed in claim 1 or 2 technique waste water, is characterized in that: the specific surface area of described zeolite is 600m
2/ more than g.
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107068228A (en) * | 2017-05-15 | 2017-08-18 | 重集团大连工程技术有限公司 | A kind of nuclear power plant's low-activity technique waste water advanced treatment apparatus and its processing method |
| CN107195352A (en) * | 2017-05-24 | 2017-09-22 | 中国核电工程有限公司 | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system |
| CN110444310A (en) * | 2019-07-17 | 2019-11-12 | 中国原子能科学研究院 | A kind of radioiodine treatment of wastes produced method |
| CN110467179A (en) * | 2018-05-09 | 2019-11-19 | 上海核工程研究设计院有限公司 | A method of active carbon is handled with nuclear facilities radioactive liquid waste chemical flocculation |
| CN111524633A (en) * | 2020-04-28 | 2020-08-11 | 一重集团大连工程技术有限公司 | Volume reduction treatment method for radioactive organic waste |
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| CN110444310A (en) * | 2019-07-17 | 2019-11-12 | 中国原子能科学研究院 | A kind of radioiodine treatment of wastes produced method |
| CN111524633A (en) * | 2020-04-28 | 2020-08-11 | 一重集团大连工程技术有限公司 | Volume reduction treatment method for radioactive organic waste |
| CN111524633B (en) * | 2020-04-28 | 2023-08-01 | 一重集团大连工程技术有限公司 | Volume reduction treatment method for radioactive organic waste |
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Application publication date: 20150826 |