CN111613358B - Nuclear power station nuclear island waste liquid treatment control method with higher economy - Google Patents
Nuclear power station nuclear island waste liquid treatment control method with higher economy Download PDFInfo
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- CN111613358B CN111613358B CN202010264907.4A CN202010264907A CN111613358B CN 111613358 B CN111613358 B CN 111613358B CN 202010264907 A CN202010264907 A CN 202010264907A CN 111613358 B CN111613358 B CN 111613358B
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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
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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
- G21F9/08—Processing by evaporation; by distillation
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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
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
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Abstract
The nuclear island waste liquid treatment control method can effectively achieve the best economy of desalting and evaporating treatment, and maximizes economic benefit under the condition of meeting the waste emission requirement. The method comprises the following steps: s1: using desalination treatment cost estimation: s2: using evaporation process cost estimation: s3, balancing point of desalting cost and evaporating cost comparison: s4, selecting a waste liquid treatment control method.
Description
Technical Field
The technology relates to the technical field of nuclear power station chemistry, in particular to a more economical nuclear island waste liquid treatment control method of a nuclear power station.
Background
The nuclear island waste liquid treatment system (hereinafter referred to as TEU) of the nuclear power plant is used for receiving waste liquid from each system of the nuclear island and storing, monitoring and treating the waste liquid. The waste liquid is filtered, desalted or evaporated and monitored and then discharged to a nuclear island waste liquid discharge system (TER for short), and the concentrated solution produced by evaporation is sent to a solid waste treatment system (TES for short) for barreling and solidification.
According to the content of chemical impurity ions and radioactivity level of the waste liquid, the treatment modes of filtration, desalination and evaporation are adopted, and the general treatment modes of the domestic M310 nuclear power units such as Fuqing nuclear power machines 1-4 are as follows:
TABLE 1
For the waste liquid with the total gamma specific activity less than 1MBq/t, the radioactivity meets the discharge requirement, so that the waste liquid can be discharged to a nuclear island waste liquid discharge System (SEL) through filtration treatment; for the waste liquid with the total gamma specific activity not less than 1MBq/t, if the content of chemical impurity ions is low (Na + < 10mg/kg and Ca 2+ By desalting treatment, if the content of chemical impurity ions is high (Na) + Not less than 10mg/kg or Ca 2+ Not less than 4 mg/kg) is treated by evaporation. The desalting loop of the nuclear island waste liquid treatment system of the domestic M310 nuclear power unit such as Fuqing nuclear power machine No. 1-4 generally adopts a mode of connecting a cation exchange resin bed and a mixed ion exchange resin bed in series, and the main purpose of limiting the sodium and calcium content of the inlet of the desalting bed is to protect the resin bed and prevent the desalting bed from being failed too early due to high impurity ion content.
However, evaporating the waste liquid will produce a concentrate, which is sent to a solid waste treatment system (TES) for barrel solidification, which also costs a significant amount of operating cost-about 2.65m per tank 3 The curing cost of the concentrated solution of the evaporator (hereinafter referred to as TEU001 EV) of the nuclear island waste liquid treatment system is about 8 ten thousand yuan, and the post-treatment cost is about 112 ten thousand yuan. Thus, a condition that can meet the waste discharge requirement is exploredThe nuclear island waste liquid treatment control method which effectively gives consideration to the optimal economy of desalting and evaporation treatment is significant.
Disclosure of Invention
The invention aims at: the nuclear island waste liquid treatment control method can effectively achieve the best economy of desalting and evaporating treatment, and maximizes economic benefit under the condition of meeting the waste emission requirement.
The technical scheme of the invention is as follows: a more economical nuclear island waste liquid treatment control method for a nuclear power station comprises the following steps:
s1: using desalination treatment cost estimation:
the content of sodium ions in the wastewater to be treated is set to be X (mg/kg), the concentration of boron is set to be Y (mg/kg), and the content of calcium ions is not considered; the total of the columns of TEU001DE and TEU002DE contains 1500+1500 x 0.3636= 2015.4 (L) of cationic resin, 2015.4L x 1.90 eq/L= 3886.26 mol=89384 g of sodium ions are exchanged, and the volume of the TEU process wastewater treated by the column of TEU001/002DE resin is equal to
Resin cost of purchasing a list of TEU001DE and TEU002 de=1500×80+150=345000 (yuan); the cost for curing the waste resin of one row of TEU001DE and TEU002DE is 173280 yuan, and the cost for post-treating the solid waste resin of one row of TEU001DE and TEU002DE is 2400000 yuan;
therefore, desalting treatment is used
The cost of nuclear island wastewater is 345000+173280+2400000= 2918280 yuan;
s2: using evaporation process cost estimation:
one-pot TEU001EV had a volume of 2.65m 3 Concentrating until boron concentration reaches 40000mg/kg, and processing
(t) the number of times the TEU process wastewater needs to be evaporated is: />
The cost of curing one tank of TEU001EV is 80860 yuan, and the solid waste cost of post-treating one tank of TEU001EV is 1120000 yuan;
so that evaporation is used for treatment
The cost estimation of TEU process wastewater is: />
S3, balancing point of desalting cost and evaporating cost comparison:
from the following components
The method can obtain: 2.89 x=y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 2.89 times of the sodium concentration, the desalting cost is equal to the evaporating cost;
(2) When the boron concentration is less than 2.89 times of the sodium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 2.89 times of the sodium concentration, the desalting cost is less than the evaporation cost;
similarly, if the content of calcium ions in the wastewater to be treated is X' (mg/kg) and the concentration of boron is Y (mg/kg), the content of sodium ions is not considered, the method can be used for solving the following problems: 3.33 x' =y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 3.33 times of the calcium concentration, the desalting cost is equal to the evaporation cost;
(2) When the boron concentration is less than 3.33 times of the calcium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 3.33 times of the calcium concentration, the desalting cost is less than the evaporating cost.
S4, selecting a waste liquid treatment control method
The method comprises the following steps:
(1) When the total gamma specific activity is less than 1MBq/t, a filtering method is adopted to treat nuclear island waste liquid of the nuclear power station;
(2) When the total gamma specific activity is more than or equal to 1 MBq/t;
(2.1) when Na < + > is less than 10mg/kg and Ca < 2+ > is less than 4mg/kg, treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2) when Na+ > 10mg/kg or Ca2+ > 4mg/kg,
(2.2.1) if B is more than or equal to Na which is 2.89 and B is more than or equal to Ca which is 3.33, treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2.2) if B is less than Na 2.89 or B is less than Ca 3.33, adopting an evaporation method to treat nuclear island waste liquid of the nuclear power station;
in S4, B represents the boron concentration.
In the step S1, the TEU001DE is a cation exchange resin bed.
The resin is Rohm and Haasirn77 hydrogen type positive resin,
the loading was 1500L.
The purchase price of the resin is 80 yuan/L.
In S1, TEU002DE is a mixed ion exchange resin bed.
In the S1, the resin is Rohm and Haasirn160 hydrogen type mixed resin.
In the S1, the loading is 1500L and the purchase price is 150 yuan/L
In S1, the TEU001DE accounts for 36.36%.
The invention has the remarkable effects that: the method can effectively give consideration to the optimal economy of desalting and evaporating treatment of the nuclear island waste liquid treatment system, and maximizes economic benefit under the condition of meeting the waste emission requirement.
Drawings
FIG. 1 is a schematic diagram of economical efficiency (sodium ions) of the existing TEU waste liquid treatment mode of Fuqing nuclear power;
FIG. 2 is a schematic diagram of economical efficiency (calcium ions) of the existing TEU waste liquid treatment mode of Fuqing nuclear power;
FIG. 3A schematic diagram of economical (sodium ion) efficiency of TEU waste liquid treatment mode in the control method
FIG. 4 is a schematic diagram of economical (calcium ion) efficiency of TEU waste liquid treatment mode in the control method
Detailed Description
The purification capacity, evaporation and desalination economy of the desalination bed of the nuclear island waste liquid treatment system are calculated, compared and demonstrated, so that a more economical control method is provided.
The cation exchange resin bed (TEU 001 DE) of the Fuqing nuclear power unit 1-4 nuclear island waste liquid treatment system is provided with Rohm and Haasirn77 hydrogen type cation resin, the loading amount is 1500L, the purchase price of the resin is 80 yuan/L, and the exchange capacity of the cation resin is 1.90eq/L; the resin contained in the mixed ion exchange resin bed (TEU 002 DE) is Rohm and Haasirn160 hydrogen type mixed resin, the containing amount is 1500L, the purchase price is 150 yuan/L, wherein the cationic resin accounts for 36.36 percent, and the cationic resin exchange capacity is 1.90eq/L. The content of sodium ions in the wastewater to be treated is X (mg/kg), the concentration of boron is Y (mg/kg), the content of calcium ions is not considered, and the calculation is simplified
A more economical nuclear island waste liquid treatment control method for a nuclear power station comprises the following steps:
s1: using desalination treatment cost estimation:
the total of one row of TEU001DE and TEU002DE contains 1500+1500 x 0.3636= 2015.4 (L) positive resin, 2015.4L x 1.90 eq/L= 3886.26 mol=89384 g sodium ions can be exchanged, and the volume of the TEU process wastewater which can be treated by the one row of TEU001/002DE resin is
Resin cost of purchasing a list of TEU001DE and TEU002 de=1500×80+150=345000 (yuan); according to engineering practice, the cost for curing a row of waste resins of TEU001DE and TEU002DE is 173280 yuan, and the solid waste cost for post-treating a row of waste resins of TEU001DE and TEU002DE is 2400000 yuan;
therefore, desalting treatment is used
The cost of nuclear island wastewater is about 345000+173280+2400000= 2918280 yuan.
S2: using evaporation process cost estimation:
one-pot TEU001EV had a volume of 2.65m 3 ConcentratingTo boron concentration of 40000mg/kg, then the treatment
(t) the number of times the TEU process wastewater needs to be evaporated is: />
Steam heating of a conventional island auxiliary steam distribution system (hereinafter referred to as SVA) is used for TEU001EV evaporation, and steam of the SVA mainly comes from exhaust steam of a main steam system (hereinafter referred to as VVP) of a unit, so that the cost of heating the TEU001EV is neglected; according to engineering practice, the cost for solidifying one-pot TEU001EV is 80860 yuan, and the cost for post-treating one-pot TEU001EV is 1120000 yuan.
So that evaporation is used for treatment
The cost estimation of TEU process wastewater is: />
S3, balancing point of desalting cost and evaporating cost comparison:
from the following components
The method can obtain: 2.89 x=y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 2.89 times of the sodium concentration, the desalting cost is equal to the evaporating cost;
(2) When the boron concentration is less than 2.89 times of the sodium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 2.89 times of the sodium concentration, the desalting cost is less than the evaporating cost.
Similarly, the content of calcium ions in the wastewater to be treated is X' (mg/kg), the concentration of boron is Y (mg/kg), the sodium ion content is not considered, the calculation is simplified, and the same can be found: 3.33 x' =y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 3.33 times of the calcium concentration, the desalting cost is equal to the evaporation cost;
(2) When the boron concentration is less than 3.33 times of the calcium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 3.33 times of the calcium concentration, the desalting cost is less than the evaporating cost.
S4, selecting a new method
The current nuclear island waste liquid treatment mode of the M310 nuclear power unit in China is as follows: desalting with sodium less than 10mg/kg and calcium less than 4mg/kg, evaporating with sodium greater than 10mg/kg or calcium greater than 4mg/kg, and the economy is shown in FIG. 3 and FIG. 4, and can be summarized in the following table
TABLE 2
The following method is adopted:
(1) When the total gamma specific activity is less than 1MBq/t, a filtering method is adopted to treat nuclear island waste liquid of the nuclear power station
(2) When the total gamma specific activity is more than or equal to 1MBq/t,
(2.1) when Na + < 10mg/kg and Ca 2+ Less than 4mg/kg, and treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2) when Na + Not less than 10mg/kg or Ca 2+ When the weight of the powder is more than or equal to 4mg/kg,
(2.2.1) if B is more than or equal to Na which is 2.89 and B is more than or equal to Ca which is 3.33, treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2.2) if B is less than Na 2.89 or B is less than Ca 3.33, adopting an evaporation method to treat nuclear island waste liquid of the nuclear power station;
wherein B represents the boron concentration.
Claims (7)
1. A more economical nuclear island waste liquid treatment control method for a nuclear power station is characterized by comprising the following steps: the method comprises the following steps:
s1: using desalination treatment cost estimation:
the content of sodium ions in the wastewater to be treated is X (mg/kg), and the boron concentration isY (mg/kg), irrespective of the calcium ion content; the total of the columns of TEU001DE and TEU002DE contains 1500+1500 x 0.3636= 2015.4 (L) of cationic resin, 2015.4L x 1.90 eq/L= 3886.26 mol=89384 g of sodium ions are exchanged, and the volume of the TEU process wastewater treated by the column of TEU001/002DE resin is equal to
Resin cost of purchasing a list of TEU001DE and TEU002 de=1500×80+150 element=345000 element; the cost for curing the waste resin of one row of TEU001DE and TEU002DE is 173280 yuan, and the cost for post-treating the solid waste resin of one row of TEU001DE and TEU002DE is 2400000 yuan;
therefore, desalting treatment is used
The cost of nuclear island wastewater is 345000+173280+2400000= 2918280 yuan;
s2: using evaporation process cost estimation:
one-pot TEU001EV had a volume of 2.65m 3 Concentrating until boron concentration reaches 40000mg/kg, and processing
(t) the number of times the TEU process wastewater needs to be evaporated is: />
The cost of curing one tank of TEU001EV is 80860 yuan, and the solid waste cost of post-treating one tank of TEU001EV is 1120000 yuan;
so that evaporation is used for treatment
(t) cost estimation of TEU process wastewater: />
S3, balancing point of desalting cost and evaporating cost comparison:
from the following components
The method can obtain: 2.89 x=y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 2.89 times of the sodium concentration, the desalting cost is equal to the evaporating cost;
(2) When the boron concentration is less than 2.89 times of the sodium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 2.89 times of the sodium concentration, the desalting cost is less than the evaporation cost;
similarly, if the content of calcium ions in the wastewater to be treated is X' (mg/kg) and the concentration of boron is Y (mg/kg), the content of sodium ions is not considered, the method can be used for solving the following problems: 3.33 x' =y, i.e. when TEU is to treat wastewater:
(1) When the boron concentration is equal to 3.33 times of the calcium concentration, the desalting cost is equal to the evaporation cost;
(2) When the boron concentration is less than 3.33 times of the calcium concentration, the desalting cost is greater than the evaporating cost;
(3) When the boron concentration is more than 3.33 times of the calcium concentration, the desalting cost is less than the evaporation cost;
s4, selecting a waste liquid treatment control method
The method comprises the following steps:
(1) When the total gamma specific activity is less than 1MBq/t, a filtering method is adopted to treat nuclear island waste liquid of the nuclear power station;
(2) When the total gamma specific activity is more than or equal to 1 MBq/t;
(2.1) when Na < + > is less than 10mg/kg and Ca < 2+ > is less than 4mg/kg, treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2) when Na+ > 10mg/kg or Ca2+ > 4mg/kg,
(2.2.1) if B is more than or equal to Na which is 2.89 and B is more than or equal to Ca which is 3.33, treating nuclear island waste liquid of the nuclear power station by adopting a desalting method;
(2.2.2) if B is less than Na 2.89 or B is less than Ca 3.33, adopting an evaporation method to treat nuclear island waste liquid of the nuclear power station;
in S4, B represents boron concentration
In the step S1, TEU002DE is a mixed ion exchange resin bed;
in the step S1, the TEU001DE is a cation exchange resin bed.
2. A more economical nuclear island waste liquid treatment control method for a nuclear power plant according to claim 1, characterized in that: the resin is Rohm and Haasirn77 hydrogen type cationic resin.
3. A more economical nuclear island waste liquid treatment control method for a nuclear power plant according to claim 2, characterized in that: the TEU001DE resin loading was 1500L.
4. A more economical nuclear island waste liquid treatment control method for a nuclear power plant according to claim 2, characterized in that: the purchase price of the resin is 80 yuan/L.
5. A more economical nuclear island waste liquid treatment control method for a nuclear power plant according to claim 1, characterized in that: in the S1, the resin is Rohm and Haasirn160 hydrogen type mixed resin.
6. The more economical nuclear island waste liquid treatment control method of the nuclear power station according to claim 5, wherein the method comprises the following steps: in the step S1, the TEU002DE loading is 1500L and the purchase price is 150 yuan/L.
7. The more economical nuclear island waste liquid treatment control method of the nuclear power station according to claim 5, wherein the method comprises the following steps: in S1, the TEU001DE accounts for 36.36%.
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11118990A (en) * | 1997-10-14 | 1999-04-30 | Hitachi Ltd | Method for treating radioactive liquid waste |
| JP2006205096A (en) * | 2005-01-28 | 2006-08-10 | Shimane Univ | Salt-removing method of soil containing salts |
| CN103400626A (en) * | 2013-07-02 | 2013-11-20 | 中国核电工程有限公司 | Method for processing waste liquid containing Ag-110m of nuclear power plant |
| CN105174596A (en) * | 2015-05-18 | 2015-12-23 | 南京万德斯环保科技有限公司 | Efficient and economical organic poisonous wastewater treatment method |
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2020
- 2020-04-07 CN CN202010264907.4A patent/CN111613358B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11118990A (en) * | 1997-10-14 | 1999-04-30 | Hitachi Ltd | Method for treating radioactive liquid waste |
| JP2006205096A (en) * | 2005-01-28 | 2006-08-10 | Shimane Univ | Salt-removing method of soil containing salts |
| CN103400626A (en) * | 2013-07-02 | 2013-11-20 | 中国核电工程有限公司 | Method for processing waste liquid containing Ag-110m of nuclear power plant |
| CN105174596A (en) * | 2015-05-18 | 2015-12-23 | 南京万德斯环保科技有限公司 | Efficient and economical organic poisonous wastewater treatment method |
Non-Patent Citations (2)
| Title |
|---|
| A review of desalting process techniques and economic analysis of the recovery of salts from retentates;Kim, Dae Hyun;《Desalination》;20111231;第270卷(第1-3期);第1-8页 * |
| 核电站中低放射性废液治理技术研究;李心砚 等;《设计与计算》;20181231(第1期);第9-14页 * |
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