CN116168867A - Control method for removing boron at end of service life of primary loop coolant of nuclear power plant - Google Patents

Control method for removing boron at end of service life of primary loop coolant of nuclear power plant Download PDF

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CN116168867A
CN116168867A CN202211695161.8A CN202211695161A CN116168867A CN 116168867 A CN116168867 A CN 116168867A CN 202211695161 A CN202211695161 A CN 202211695161A CN 116168867 A CN116168867 A CN 116168867A
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boric acid
resin
exchanger
anion exchanger
anion
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胡海
杨兴龙
王旭初
苏凯
强浩
孔亮
章书维
王良明
郑庆云
杜元生
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Jiangsu Nuclear Power Corp
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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
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J47/00—Ion-exchange processes in general; Apparatus therefor
    • B01J47/02—Column or bed processes
    • B01J47/04—Mixed-bed processes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant

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Abstract

The invention belongs to the field of primary loop water quality control of nuclear power plants, and particularly relates to a control method for removing boron at the end of service life of primary loop coolant of a nuclear power plant. When the resin in the anion resin exchanger is used at the end of the cycle life of the first round of fuel, the concentration of boric acid is reduced to be within the interval of 150mg/L to 60mg/L, and the anion resin exchanger is independently put into operation; when the resin in the anion resin exchanger is used at the end of the second round of fuel cycle life, the concentration of boric acid is reduced to 120 mg/L-60 mg/L, and the anion resin exchanger is independently put into operation; when the concentration of boric acid is reduced to be within 60mg/L, the cation exchanger and the anion exchanger are put into operation in a combined mode, when the concentration of total alkali metal or dissolved hydrogen in a first loop is in the lower limit of a control value, the cation exchanger is temporarily taken out of operation, and the cation exchanger is put into operation continuously after the water quality is stable. The invention can effectively avoid the generation of water quality deviation and reduce the solid waste amount of the radioactive resin of the primary loop.

Description

Control method for removing boron at end of service life of primary loop coolant of nuclear power plant
Technical Field
The invention belongs to the field of primary loop water quality control of nuclear power plants, and particularly relates to a control method for removing boron at the end of service life of primary loop coolant of a nuclear power plant.
Background
Pressurized water reactor nuclear power units control core reactivity during normal operation by boric acid, in natural boric acid 10 B abundance of 19.78%, with a larger neutron absorption cross section (3837 dB), and neutron generation 10 B(n,α) 7 Li reacts and is distributed at various parts of a loop along with the circulation of the main pump. The boric acid concentration in the coolant is high in the early and middle stages of the fuel cycle, and the boron concentration in the coolant is reduced by a water filling and draining method to compensate for burnup, but at the end of the fuel cycle, a large amount of wastewater is generated by the adjustment method, the boron concentration is slowly reduced, the reactor core reactivity is not maintained, and fluctuation of reactor power is caused. The primary loop coolant of the nuclear power plant adopts an OH-type (namely negative) ion exchange resin bed to remove boron, and when the boric acid concentration in the coolant meets the operation requirement of the reactor, the boron removal resin bed is taken out of operation.
In actual operation, it was found that at the end of life, problems exist in operating the anion exchange resin bed to remove the primary loop of boric acid:
1. boric acid concentration is not in line with theoretical reduction, reactor core reactivity is easy to fluctuate, water change of a primary loop is increased, and more radioactive wastewater is generated;
2. the resin exchange capacity in the anion resin exchanger is not exhausted, and early replacement brings economic loss and increases radioactive solid waste.
In order to improve the boron removal efficiency when the anion resin exchanger is put into operation and reduce the production of radioactive wastewater and radioactive solid waste, a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant is provided.
Disclosure of Invention
The invention aims to provide a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant.
The technical scheme for realizing the purpose of the invention comprises the following steps:
a method of controlling boron removal at the end of the life of a primary loop coolant of a nuclear power plant, the method comprising:
step 1: respectively loading cation exchange resin and anion exchange resin in a cation exchanger and an anion exchanger, after resin loading is finished, washing the resin with desalted water to be qualified, closing an outlet valve and an inlet valve, and placing the resin in a standby state;
step 2: when the resin in the anion exchanger is used at the end of the cycle life of the first round of fuel, and the boric acid concentration in the primary loop coolant is reduced to a range of 150 mg/L-60 mg/L, after the anion exchanger is washed to be qualified, the anion exchanger is independently put into operation, the primary loop boric acid is removed, and the operation flow is calculated according to an operation flow formula;
step 3: when the resin in the anion exchanger is used at the end of the second round of fuel circulation life, the boric acid concentration in the primary loop coolant is reduced to 120 mg/L-60 mg/L, and after the anion exchanger is washed to be qualified, the anion exchanger is independently put into operation, and the operation flow is calculated according to an operation flow formula;
step 4: when the boric acid concentration in the coolant of the first loop is reduced to be within 60mg/L, the cation exchanger is put into operation in combination with the anion exchanger after being washed to be qualified, the operation flow is calculated according to an operation flow formula, and when the total alkali metal or dissolved hydrogen concentration of the first loop is in the lower limit of a control value, the cation exchanger is temporarily taken out of operation, and the operation is continued after the water quality is stable.
The operation flow formula is as follows:
Figure BDA0004022208060000031
wherein ρ is 1 Boric acid concentration, X is the operational flow.
The method further comprises the steps of:
step 5: when the cation exchanger and the anion exchanger are put into operation in a combined mode and the reactor power cannot be stabilized, the ammonia concentration is reduced on the premise of meeting the hydrogen dissolution control; on the premise of meeting the purification requirement, the over-bed flow of the KBE of the primary loop coolant purification system is reduced until the reactor power is stable.
The method further comprises the steps of:
step 6: and unloading the resin after the second round of fuel circulation is finished and the operation of the anion exchanger is finished, unloading the resin after the exchange capacity of the cation exchanger is exhausted, reloading the resin, and placing the anion exchanger in a standby state after the demineralized water is washed to be qualified.
The washing modes of the anion exchanger in the step 2 and the step 3 are as follows: preparing boric acid solution with the same concentration as that of the main loop boric acid in the anion exchanger, and independently putting the anion exchanger into operation after the anion exchanger is washed to be qualified.
The washing mode of the cation exchanger in the step 4 is as follows: and preparing boric acid solution with the same concentration as that of the main loop boric acid in the cation exchanger, and after the cation exchanger is washed to be qualified, putting the cation exchanger and the anion exchanger into operation in a combined way.
The beneficial technical effects of the invention are as follows:
1. the invention provides and solves the problem that the boric acid concentration of the primary loop of the nuclear power plant at the end of the life does not accord with the theoretical reduction through theoretical analysis and experimental verification.
2. The method optimizes the boric acid concentration control method at the end of the service life, and improves the economical efficiency of the system operation while maintaining the functional requirements of the original system design.
3. The invention improves the boron removal efficiency of the anion resin and reduces the radioactive solid waste and radioactive effluent discharge.
4. The invention removes the boric acid of the first loop by the joint operation of the negative resin and the positive resin, can reduce the opening of the leakage flow, reduces the loss of hydrogen dissolution of the first loop, and ensures the safety of the water quality of the first loop.
5. The invention provides a time for the removal of boric acid by putting the anion exchanger into operation at the end of the life of both fuel cycles.
Drawings
FIG. 1 is a flow chart of a control process for removing boron at the end of the life of a primary loop coolant of a nuclear power plant;
in the figure: 1-a reactor pressure vessel; 2-a steam generator; 3-a main pump; 4-a loop purification system KBE; 5-degasser; 6-coolant storage system cation exchange bed KBB10AT001; 7-coolant storage system anion exchange bed KBB10AT002.
Detailed Description
The invention is described in further detail below with reference to the drawings and examples.
The invention provides a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant, wherein a coolant storage system comprises a cation exchanger and an anion exchanger, and the control method comprises the following steps:
the coolant storage system (KBB) comprises two ion exchangers, the cation exchanger (KBB 10AT 001) being loaded with a cationic resin of the H type, when the total alkali metal concentration (Li + /Na + /K + ) When exceeding standard, part of the first-loop coolant is led into a cation exchanger, H groups in the cation resin and alkali metal ions in the first-loop coolant are subjected to exchange reaction, and the first-loop coolant for removing the alkali metal ions is returned to the first-loop by an upper charge pump, so that the total alkali metal concentration of the first-loop is maintainedAnd the chemical working condition of the primary circuit water is maintained.
The anion exchanger (KBB 10AT 002) is loaded with OH-type anion resin, can carry out exchange reaction with borate ions in a loop coolant and is used for removing boron AT the end of the service life of fuel, when the concentration of boric acid in the loop coolant is low, the mode of changing water and diluting boric acid has no great effect on reducing the concentration of boron, excessive waste liquid can be generated, the burden of a three-waste system is increased, in order to maintain the power of a reactor, the boron is removed in an ion exchange mode, part of the loop coolant is introduced into the anion exchanger, and the borate ions are removed and then returned to the loop by an upper charge pump, so that the power of the reactor is kept stable.
Both ion exchangers are provided with a drain line, an exhaust line, a compressed air and chemical demineralized water supply line, a hydraulic flushing drain line, a chemical sampling line, and a hydraulic unloading drain line.
The invention provides a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant, which comprises the following steps of:
boric acid is a monobasic weak acid with ionization constant K a ＝5.8×10 -10 Mainly comprises orthoboric acid H in aqueous solution 3 BO 3 Monoborate B (OH) 4 - Triborate B 3 O 3 (OH) 4 - Tetraborate B 4 O 3 (OH) 4 2- The composition is complex and has an inseparable relationship with the boric acid concentration. When a nuclear power unit reactor in China runs under power, the pH value of a first loop coolant is adjusted by adding KOH, and ammonia water added by irradiation decomposition is utilized to generate hydrogen, so that the first loop is maintained under a weak alkaline reductive water chemical working condition, and the pH value is maintained 300℃ Maintained within the range of 7.0-7.2. The alkaline environment necessarily affects the ionization balance of boric acid, particularly at the end of the fuel cycle, which is particularly evident when the anion exchanger is put into operation, and as the pH increases, the absorption efficiency of the resin for boric acid decreases, and it is necessary to moderately adjust the pH of the purified coolant in order to increase the efficiency of the anion resin for removing boric acid.
(1) Coolant storage system anion exchanger KBB10AT002 has low boron removal efficiency
When the reactor is operating normally, according to theoretical calculation, the boric acid concentration of the first loop is reduced AT 22mg/L every day, and AT the end of life, if the power of the reactor is kept stable, the anion exchanger KBB10AT002 is needed to be put into the first loop for removing boron AT the flow rate of X kg/s, and the current boric acid concentration is assumed to be ρ 1 The leakage flow rate is 0.6kg/s, and the leakage monitoring flow rate of the main pump is 0.8kg/s according to the operation rules, and the calculation formula of the operation flow rate X of the anion exchanger KBB10AT002 is as follows:
Figure BDA0004022208060000061
i.e. < ->
Figure BDA0004022208060000062
Formula 1
In the final stage of a certain fuel cycle, the concentration of boric acid in a loop is 150mg/L, in order to maintain the power of a reactor, the KBB10AT002 of the anion exchanger is connected into the loop AT a flow rate of 1.5kg/s according to a calculation formula to remove boron, and in the actual operation process, the flow rate of the KBB10AT002 of the anion exchanger is regulated to 4kg/s to maintain the power; the next day and early shift adjust the flow rate of the anion exchanger KBB10AT002 to 5.2kg/s and the down-flow rate to 1.5kg/s, so that the power can be maintained, and the boron removal flow rate and the down-flow rate are both larger than theoretical calculated values.
And because of the hydrogen reduction requirement at the end of the life, the hydrogen dissolution of the first loop is only 2.3mg/L, and the continuous opening of the leakage is easy to lead the hydrogen dissolution to be lower than the control value of 2.2mg/L, so that the leakage flow is reduced as much as possible.
To find out the reason for the low boron removal efficiency of the anion exchanger KBB10AT002, the boric acid concentration of the first circuit and the outlet of the anion exchanger KBB10AT002 is counted as follows:
TABLE 1 boric acid concentration AT the outlet of the first and KBB10AT002 cathode beds and pH of the first circuit 25℃
Figure BDA0004022208060000063
As can be seen from table 1, when the OH-type anion resin bed is put into operation to remove the primary loop boric acid, the bed outlet has boric acid, and the ratio of the boric acid at the bed outlet to the boric acid at the main loop is higher and higher, possibly related to the gradual rise of the pH of the primary loop, the increase of the pH reduces the capacity of the anion resin to exchange boric acid, and the efficiency of removing boric acid from the anion resin is reduced; and the main circuit boric acid value is very low, so that the boric acid at the outlet of the bed cannot be ignored when the purification is calculated at the end of the service life.
In order to improve the efficiency of the anion resin bed in removing boric acid, the cation resin exchanger was selected to be put into operation at the same time, and the concentration of boric acid at the outlet of the anion resin bed at the end of a certain period of service was tracked, and the results are shown in Table 2.
TABLE 2 concentration of boric acid at the outlet of anion exchange bed when anion and cation resin beds are simultaneously operated, mg/L
Figure BDA0004022208060000071
As can be seen from Table 2, when the anion and cation resin exchangers are put into operation jointly, the removal of the total alkali metal of the first circuit, namely the pH value reduction, is carried out, and meanwhile, the removal of the boric acid of the first circuit, the removal efficiency of the anion resin on the boric acid can be effectively improved, and particularly, after the concentration of the boric acid in the first circuit coolant is less than 60 mg/L.
(2) KBE negative resin boric acid drainage belt of one-loop coolant purification system
A primary coolant purification system (KBE) continuously purifies impurity ions in primary coolant at a flow rate of 8.3kg/s, and an OH-type anion resin in the purification system is saturated with boric acid at the initial stage of starting up to become boric acid saturated resin.
In alkaline environments, boric acid reacts to form complex B (OH) 4 - 、B 3 (OH) 10 - 、B 2 (OH) 7 - 、B 4 (OH) 14 2- Etc., the reaction formula is as follows:
B(OH) 3 +OH - ＝B(OH) 4 -
2B(OH) 3 +OH - ＝B 2 (OH) 7 -
3B(OH) 3 +OH - ＝B 3 (OH) 10 -
4B(OH) 3 +OH - ＝B 2 (OH) 14 2-
as the reactor operates, the concentration of boric acid in the primary circuit gradually decreases, and when the boron-removing resin bed is put into operation, the concentration of boric acid in the primary circuit further decreases, and orthoboric acid (B (OH) is generated by the above reaction type 3 ) The direction of the flow of the coolant through the anionic resin bed, and the boric acid adsorbed in the anionic resin bed of the first loop coolant purification system (KBE) is polyborate ions, the resin bed releases boric acid to the first loop, namely, the boric acid is discharged.
To explain the phenomenon that boric acid is discharged from the boric acid saturated anion resin, when the anion exchanger KBB10AT002 of the coolant storage system is put into operation, the boric acid concentration is simultaneously analyzed by sampling the outlet and the inlet of the anion exchanger KBB10AT002 of the coolant storage system, and the boric acid concentration AT the inlet of the anion exchanger KBB10AT002 of the coolant storage system is calculated according to the formula (I), and the result is as follows:
TABLE 3 boric acid concentration at the outlet and inlet of the first circuit and anion apparatus (unit, mg/L)
Figure BDA0004022208060000081
As can be seen from table 3, the actual boric acid AT the inlet of the anion exchanger KBB10AT002 of the coolant storage system is higher than the theoretical concentration AT the inlet, i.e. the boric acid source is continuously released, while the inlet of the anion exchanger KBB10AT002 of the coolant storage system is derived from the outlet of the KBE of the primary coolant purification system, which indicates that boric acid saturation of the anion resin takes place when the boric acid concentration in the coolant is lower than the saturated boric acid concentration of the anion exchange resin of the KBE system. The discharge rate is related to the concentration of boric acid in the first circuit and the concentration of boric acid entering the anion resin exchanger, and the difference between the two concentrations is positive, and also related to the flow rate passing through the resin bed, so that the discharge rate of the excessive bed is reduced, and the discharge rate of boric acid can be reduced.
The invention provides a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant, which comprises the following steps of:
1) The anion resin exchanger KBB10AT002 is filled with 2.4m3 nuclear-grade anion resin, the purchase price per cubic meter is about 10 ten thousand yuan, the price of the radioactive solid waste per cubic meter is about 4 ten thousand yuan, for example, the service life of the anion resin is prolonged to 2 fuel cycles, and the purchase resin and the treatment cost can be saved by about 16.8 ten thousand yuan (10 multiplied by 1.2 multiplied by 1.2=16.8) per fuel cycle.
2) After looking up the operation curve and history data of the reactor power, when the boric acid concentration in the primary loop coolant is more than 100mg/L, the water change mode can still maintain the reactivity to ensure the stable power; through statistics history data and the working exchange capacity of the anion exchange resin to boric acid, when the anion exchange resin is used for the first fuel cycle, the concentration of boric acid in the first circuit is less than 150mg/L, the anion exchange resin KBB10AT002 is put into operation for removing boron, when the anion exchange resin is used for the second fuel cycle, the concentration of boric acid in the first circuit is less than 120mg/L for removing boron, the reactor core reactivity can be maintained, and the power of the reactor is ensured not to fluctuate.
The invention provides a control method for removing boron at the end of the service life of a primary loop coolant of a nuclear power plant, which specifically comprises the following steps:
step 1: respectively loading cation exchange resin and anion exchange resin in a cation exchanger KBB10AT001 and an anion exchanger KBB10AT002, after resin loading is finished, washing with desalted water to be qualified, closing an outlet valve and an inlet valve, and placing in a standby state;
step 2: when the resin in the anion exchanger is used AT the end of the cycle life of the first round of fuel, boric acid solution with the same concentration as that of main loop boric acid is prepared in the anion exchanger KBB10AT002 when the concentration of boric acid in the loop coolant is reduced to a range of 150 mg/L-60 mg/L, the anion exchanger KBB10AT002 is independently put into operation after the anion exchanger is washed to be qualified, the loop boric acid is removed, and the operation flow is calculated according to an operation flow formula (I));
step 3: when the resin in the anion exchanger is used AT the end of the second round of fuel circulation life, in the interval that the boric acid concentration in the primary circuit coolant is reduced to 120 mg/L-60 mg/L, preparing boric acid solution with the same concentration as that of main circuit boric acid in the anion exchanger KBB10AT002, and independently putting the anion exchanger KBB10AT002 into operation after the anion exchanger is washed to be qualified, wherein the operation flow is calculated according to an operation flow formula (I));
step 4: when the boric acid concentration in the primary loop coolant is reduced to be within 60mg/L, preparing boric acid solution with the same concentration as that of main loop boric acid in the cation exchanger KBB10AT001, flushing the cation exchanger KBB10AT001 to be qualified, then jointly operating with the anion exchanger (KBB 10AT 002), calculating the operating flow according to an operating flow formula (I)), and temporarily stopping the operation of the cation exchanger KBB10AT001 when the total alkali metal or dissolved hydrogen concentration of the primary loop is AT the lower limit of a control value, and continuing to operate after the water quality is stable.
Step 5: when the cation exchanger (KBB 10AT 001) and the anion exchanger (KBB 10AT 002) are jointly put into operation and the reactor power cannot be stabilized, the ammonia concentration is reduced on the premise of meeting the hydrogen dissolution control; on the premise of meeting the purification requirement, the over-bed flow of the KBE of the primary loop coolant purification system is reduced until the reactor power is stable.
Step 6: AT the end of the second round of fuel circulation, the anion exchanger KBB10AT002 is put into operation, resin is unloaded, the cation exchanger KBB10AT001 is unloaded after the exchange capacity is exhausted, resin is reloaded, and the desalting water is washed to be qualified and then is put into a standby state. And repeating the steps 2 to 6.
The method optimizes the boric acid concentration of a first loop when the anion exchanger is put into operation, reduces the use of KBB10AT002 resin, increases the replacement frequency of the anion exchanger, and prolongs the service life of KBB10AT002 to twice as much as the original service life;
the production of the radioactive solid waste of the nuclear power station is reduced, the purchase cost of resin is saved by about 12 ten thousand yuan for each fuel cycle, and the treatment cost of the radioactive solid waste is saved by 4.8 ten thousand yuan;
the boron removal efficiency of the anion exchange resin at the end of the service life is improved, the water exchange amount of a primary loop is reduced, the generation of radioactive effluent is further reduced, and a safe and stable method for controlling the reactor core reactivity at the end of the service life is provided.
TABLE 1 comparison of resin usage amount for removing boron per fuel cycle, radioactive waste water and solid waste production amount
Figure BDA0004022208060000111
The present invention has been described in detail with reference to the drawings and the embodiments, but the present invention is not limited to the embodiments described above, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present invention. The invention may be practiced otherwise than as specifically described.

Claims (6)

1. A method for controlling boron removal at the end of the life of a primary loop coolant in a nuclear power plant, the method comprising:
step 1: respectively loading cation exchange resin and anion exchange resin in a cation exchanger and an anion exchanger, after resin loading is finished, washing the resin with desalted water to be qualified, closing an outlet valve and an inlet valve, and placing the resin in a standby state;
step 2: when the resin in the anion exchanger is used at the end of the cycle life of the first round of fuel, and the boric acid concentration in the primary loop coolant is reduced to a range of 150 mg/L-60 mg/L, after the anion exchanger is washed to be qualified, the anion exchanger is independently put into operation, the primary loop boric acid is removed, and the operation flow is calculated according to an operation flow formula;
step 3: when the resin in the anion exchanger is used at the end of the second round of fuel circulation life, the boric acid concentration in the primary loop coolant is reduced to 120 mg/L-60 mg/L, and after the anion exchanger is washed to be qualified, the anion exchanger is independently put into operation, and the operation flow is calculated according to an operation flow formula;
step 4: when the boric acid concentration in the coolant of the first loop is reduced to be within 60mg/L, the cation exchanger is put into operation in combination with the anion exchanger after being washed to be qualified, the operation flow is calculated according to an operation flow formula, and when the total alkali metal or dissolved hydrogen concentration of the first loop is in the lower limit of a control value, the cation exchanger is temporarily taken out of operation, and the operation is continued after the water quality is stable.
2. The method for controlling boron removal at the end of life of a primary loop coolant of a nuclear power plant according to claim 1, wherein the operational flow formula is:
Figure FDA0004022208050000011
wherein ρ is 1 Boric acid concentration, X is the operational flow.
3. The method for controlling boron removal at the end of life of a primary loop coolant of a nuclear power plant according to claim 2, further comprising:
step 5: when the cation exchanger and the anion exchanger are put into operation in a combined mode and the reactor power cannot be stabilized, the ammonia concentration is reduced on the premise of meeting the hydrogen dissolution control; on the premise of meeting the purification requirement, the over-bed flow of the KBE of the primary loop coolant purification system is reduced until the reactor power is stable.
4. A method of controlling boron removal at the end of the life of a primary loop coolant of a nuclear power plant as claimed in claim 3, said method further comprising:
step 6: and unloading the resin after the second round of fuel circulation is finished and the operation of the anion exchanger is finished, unloading the resin after the exchange capacity of the cation exchanger is exhausted, reloading the resin, and placing the anion exchanger in a standby state after the demineralized water is washed to be qualified.
5. The method for controlling boron removal at the end of life of a primary loop coolant in a nuclear power plant according to claim 4, wherein the anion exchanger flushing mode in step 2 and step 3 is as follows: preparing boric acid solution with the same concentration as that of the main loop boric acid in the anion exchanger, and independently putting the anion exchanger into operation after the anion exchanger is washed to be qualified.
6. The method for controlling boron removal at the end of life of a primary loop coolant in a nuclear power plant according to claim 5, wherein the cation exchanger flushing mode in step 4 is as follows: and preparing boric acid solution with the same concentration as that of the main loop boric acid in the cation exchanger, and after the cation exchanger is washed to be qualified, putting the cation exchanger and the anion exchanger into operation in a combined way.
CN202211695161.8A 2022-12-28 2022-12-28 Control method for removing boron at end of service life of primary loop coolant of nuclear power plant Pending CN116168867A (en)

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