CN204577118U - The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water - Google Patents

The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water Download PDF

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Publication number
CN204577118U
CN204577118U CN201520188325.7U CN201520188325U CN204577118U CN 204577118 U CN204577118 U CN 204577118U CN 201520188325 U CN201520188325 U CN 201520188325U CN 204577118 U CN204577118 U CN 204577118U
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China
Prior art keywords
waste water
pipeline
mixing tank
tank
power plant
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Active
Application number
CN201520188325.7U
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Chinese (zh)
Inventor
游新锋
王松平
郑文俊
李俊雄
王雷
邱乙亩
张振涛
陶幼林
华小辉
饶建民
杨林月
陆炜
郑宇�
张旭
杨勇刚
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Peach Blossom River Hunan Nuclear Power Co Ltd
China Institute of Atomic of Energy
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Peach Blossom River Hunan Nuclear Power Co Ltd
China Institute of Atomic of Energy
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Abstract

The utility model relates to a kind for the treatment of apparatus of radioactive wastewater.Low for solving existing ion-exchange unit utilization rate, cause the difficult problem that secondary refuse amount significantly increases, the utility model provides the removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water.This device mainly comprises waste water temporary storage tank, fore filter, flocculating agent tank, mixing tank, activated-charcoal column and zeolite column, waste water temporary storage tank is connected with fore filter by pipeline, fore filter is connected with mixing tank by pipeline, flocculating agent tank is connected with mixing tank by pipeline, mixing tank is connected with activated-charcoal column by pipeline, and activated-charcoal column is connected with zeolite column by pipeline.Removal device of the present utility model is applicable to before technique waste water ion-exchange treatment, pre-service is carried out to technique waste water, to remove the colloidal attitude corrosion product in technique waste water, significantly improve the service efficiency of ion exchange resin, and then reduce the generation of secondary refuse.

Description

The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water
Technical field
The utility model relates to a kind for the treatment of apparatus of radioactive wastewater, particularly the removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water.
Background technology
In pressurized-water reactor nuclear power plant operational process, the primary Ioops equipment and materials be corroded is after reactor irradiation, form activating product, these corrosion products are usual after dissolving to be present in primary Ioops cooling medium with ionic state and colloidal attitude, and enter nuclear power plant's liquid waste treatment system by the leakage of nuclear power plant's chemistry volume control system and primary Ioops, be present in nuclear power plant's waste water.
At present, the process of the activating product of colloidal attitude and other nuclear power plant's waste water are equally direct by filter and ion-exchange processes, and carry out slot type monitoring discharge after wastewater treatment is qualified.So often make colloidal attitude corrosion product cause very large pressure to ion exchange resin, the utilization rate of ion-exchange unit is reduced greatly, and cause the remarkable increase of secondary refuse amount, have a strong impact on the treatment effect of ion-exchange.
Utility model content
For solving existing equipment in nuclear power plant's technique waste water process because the existence of colloidal attitude corrosion product causes ion-exchange unit utilization rate low, cause the difficult problem that secondary refuse amount significantly increases, the utility model provides the treating apparatus of a kind of nuclear power plant technique waste water.
This device mainly comprises waste water temporary storage tank, fore filter, flocculating agent tank, mixing tank, activated-charcoal column and zeolite column, waste water temporary storage tank is connected with fore filter by pipeline, fore filter is connected with mixing tank by pipeline, flocculating agent tank is connected with mixing tank by pipeline, mixing tank is connected with activated-charcoal column by pipeline, and activated-charcoal column is connected with zeolite column by pipeline.
Between described fore filter and mixing tank, wastewater flow variable valve can also be set; Between described flocculating agent tank and mixing tank, flocculating agent flow control valve can also be set.
The main flow of the treating apparatus treatment process waste water of nuclear power plant of the present utility model technique waste water is as follows:
First, the technique waste water of discharging from nuclear power plant is delivered to waste water temporary storage tank and keeps in; Waste water, after the suspended impurity that fore filter filtering may remain, with the mix and blend in mixing tank of the flocculating agent from flocculating agent tank, makes colloid wherein and fine suspension produce cohesion, forms larger glue plumage; Then make waste water be undertaken adsorbing and filtering by activated-charcoal column and zeolite column, complete the removal of colloidal attitude corrosion product in technique waste water.The technique waste water of removing colloidal attitude corrosion product can be delivered to ion-exchange processing device and be further processed
The treating apparatus of nuclear power plant of the present utility model technique waste water is applicable to before technique waste water ion-exchange treatment, pre-service is carried out to technique waste water, to remove the colloidal attitude corrosion product in technique waste water, significantly improve the service efficiency of ion exchange resin, and then reduce the generation of secondary refuse, make treated technique waste water radioactive level lower simultaneously.
Accompanying drawing explanation
The treating apparatus structural representation of Fig. 1 nuclear power plant of the present utility model technique waste water.
Reference numeral: 1. waste water temporary storage tank, 2. flocculating agent tank, 3. mixing tank, 4. activated-charcoal column, 5. zeolite column, 102. waste water discharge pumps, 103. wastewater flow variable valve, 105. fore filters, 202. flocculating agent discharge pumps, 203. flocculating agent flow control valves.
Embodiment
Below in conjunction with accompanying drawing, embodiments of the present invention are described further.
Embodiment
Figure 1 shows that the structural representation of a treating apparatus embodiment of the utility model nuclear power plant technique waste water.As seen from the figure, this device mainly comprises waste water temporary storage tank, fore filter, flocculating agent tank, mixing tank, activated-charcoal column and zeolite column; Waste water temporary storage tank is provided with a water inlet and a water delivering orifice, and is connected with fore filter by pipeline; Fore filter is connected with mixing tank by pipeline, and the pipeline between the two is provided with waste water discharge pump; Flocculating agent tank is connected with mixing tank by pipeline, and the pipeline between the two is provided with flocculating agent discharge pump; Mixing tank is connected with activated-charcoal column by pipeline; Activated-charcoal column is connected with zeolite column by pipeline.Flow control valve is provided with between described fore filter and mixing tank; Flow control valve is provided with between described flocculating agent tank and mixing tank.
Adopt above-mentioned treating apparatus to process nuclear power plant's technique waste water, wastewater treatment capacity is 300BV (i.e. 300 × 17L=5100L), and after testing, it is greater than 3000,300,6000 and 1200 respectively to the decontamination factor of Ag, Co, Cs, Sr.

Claims (3)

1. the removal device of colloidal attitude corrosion product in nuclear power plant's technique waste water, it is characterized in that: this device mainly comprises waste water temporary storage tank, fore filter, flocculating agent tank, mixing tank, activated-charcoal column and zeolite column, waste water temporary storage tank is connected with fore filter by pipeline, fore filter is connected with mixing tank by pipeline, flocculating agent tank is connected with mixing tank by pipeline, mixing tank is connected with activated-charcoal column by pipeline, and activated-charcoal column is connected with zeolite column by pipeline.
2. the removal device of colloidal attitude corrosion product in nuclear power plant as claimed in claim 1 technique waste water, is characterized in that: be provided with wastewater flow variable valve between described fore filter and mixing tank.
3. the removal device of colloidal attitude corrosion product in nuclear power plant as claimed in claim 1 technique waste water, is characterized in that: be also provided with flocculating agent flow control valve between described flocculating agent tank and mixing tank.
CN201520188325.7U 2015-03-31 2015-03-31 The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water Active CN204577118U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201520188325.7U CN204577118U (en) 2015-03-31 2015-03-31 The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201520188325.7U CN204577118U (en) 2015-03-31 2015-03-31 The removal device of colloidal attitude corrosion product in a kind of nuclear power plant technique waste water

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CN204577118U true CN204577118U (en) 2015-08-19

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104766642A (en) * 2015-03-31 2015-07-08 中国原子能科学研究院 Device for removing colloidal corrosion product in process wastewater of nuclear power plant

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104766642A (en) * 2015-03-31 2015-07-08 中国原子能科学研究院 Device for removing colloidal corrosion product in process wastewater of nuclear power plant

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