JP2009300162A - Desalter for primary cooling system and purification method for primary cooling water in nuclear power plant with pressurized water reactor - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To obtain a desalter where neither fracture nor cracking appears in an anion exchange resin even if primary cooling water containing boric acid is brought into contact with the resin. <P>SOLUTION: The desalter for a primary cooling system 8, which purifies primary cooling water in a nuclear power plant with a pressurized water reactor, is composed by including a purification means filled with a porous anion exchange resin whose pore volume is 0.05 to 0.50 mL/g of dry resin (Cl type) and also whose average pore radius is 2 to 50 nm (Cl type). The method for purifying the primary cooling water is composed by bringing the primary cooling water in the nuclear power plant with the pressurized water reactor into contact with the porous anion exchange resin whose pore volume is 0.05 to 0.50 mL/g of dry resin (Cl type) and also whose average pore radius is 2 to 50 nm (Cl type). <P>COPYRIGHT: (C)2010,JPO&INPIT

Description

  The present invention relates to a desalination apparatus for a primary cooling system of a pressurized water nuclear power plant, and a purification method for primary cooling water.

A pressurized water nuclear power plant (PWR power plant) has a primary cooling system having a nuclear reactor and a secondary cooling system that generates power by driving a turbine using steam generated by a steam generator. Connected and configured via a generator. The primary cooling water used in the primary cooling system cools the reactor and becomes high temperature and high pressure. In the steam generator, the primary cooling water at a high temperature and high pressure exchanges heat with the secondary cooling water in the secondary cooling system, and evaporates the secondary cooling water to obtain high-pressure steam. In the secondary cooling system, power is generated by driving the turbine with water vapor generated in the steam generator.
In the primary cooling system, impurities such as chloride ions and fluoride ions, fission products such as ¹³¹ I, and corrosion products such as ⁵⁸ Co, ⁶⁰ Co, nickel, and iron are removed from the primary cooling water. In order to do this, a part of the primary cooling water is led out of the reactor and processed by a desalinator of a chemical volume control (CVCS) system and a boric acid recovery (BRS) system. In the spent fuel pit water purification cooling (SFPCS) system, impurities such as chloride ions and fluoride ions contained in the primary cooling water, fission products such as ¹³¹ I, and ⁵⁸ Co, ⁶⁰ Co, The primary cooling water is purified by removing corrosion products such as nickel and iron.
For the purpose of purifying such primary cooling water, a mixed bed type desalination apparatus is installed in the CVCS system, the BRS system, and the SFPCS system. Conventionally, an invention relating to the operation of the mixed bed type desalination apparatus has been made. For example, Patent Document 1 reports an invention concerning a mixing ratio of a cation exchange resin and an anion exchange resin. In a primary cooling system desalting apparatus, a gel-type OH-type anion exchange resin is generally used as an anion exchange resin.

Boric acid is added to the primary cooling water for the purpose of controlling the critical state of the reactor fuel. In particular, during periodic inspections and fuel replacement, the boron concentration of the primary cooling water is increased to keep the fuel in a subcritical state. Then, when the operation of the PWR type power plant is resumed, primary cooling water having a higher boron concentration than normal operation is passed through the desalination apparatus of the primary cooling system, and boric acid replacement is performed. In recent years, the use of high burn-up fuel has been studied in order to improve power generation efficiency and availability. When such high burnup fuel is used, it is necessary to further increase the boron concentration of the primary cooling water when the PWR type power plant is operated and stopped.
Japanese Patent Laid-Open No. 2005-3598

However, when a boric acid solution having a boron concentration exceeding 3000 ppm is passed through the primary cooling system desalting apparatus of a PWR type power plant, for example, the filled anion exchange resin is cracked or cracked. was there. When cracks or cracks occur in the anion exchange resin, the refined resin flows out of the desalting apparatus, the differential pressure of the filter disposed at a later stage than the desalting apparatus increases, and the frequency of filter replacement increases. Thus, there have been problems such as an increase in the labor of the worker accompanying the replacement work and an increase in the amount of radioactive waste accompanying the filter disposal.
Then, this invention aims at the desalination apparatus which does not generate | occur | produce a crack or a crack in an anion exchange resin even if it makes primary cooling water containing a boric acid contact.

The primary cooling system desalination apparatus of the pressurized water nuclear power plant of the present invention is a desalination apparatus for purifying the primary cooling water of the pressurized water nuclear power plant, and has a pore volume of 0.05 to 0.50 mL / g. -Purified by contacting primary cooling water with a porous anion exchange resin having a dry resin (Cl type) and an average pore radius of 2 to 50 nm (Cl type).
The primary cooling system desalination apparatus of the present invention is preferably installed in at least one of a chemical volume control system, a boric acid recovery system, and a spent fuel pit water purification cooling system.

  The method for purifying primary cooling water of a pressurized water nuclear power plant according to the present invention has a pore volume of 0.05 to 0.50 mL / g-dry resin (Cl type) and an average pore radius of 2 to 50 nm (Cl The primary cooling water of a pressurized water nuclear power plant is brought into contact with the porous anion exchange resin.

  According to the primary cooling system desalination apparatus of the pressurized water nuclear power plant of the present invention, it is possible to prevent cracking and cracking of the filled anion exchange resin even when the primary cooling water containing boric acid is brought into contact. .

The present invention relates to a porous anion exchange resin (hereinafter, referred to as a porous anion exchange resin having a pore volume of 0.05 to 0.50 mL / g-dry resin (Cl form) and an average pore radius of 2 to 50 nm (Cl form). This is a primary cooling system desalination device that purifies the primary cooling water by contacting it with a porous anion exchange resin). An example of an embodiment of the present invention will be described with reference to FIG. FIG. 1 is a schematic diagram showing a primary cooling system 8 of a PWR type power plant. As shown in FIG. 1, the primary cooling system 8 includes a primary cooling water circulation line 10, a CVCS system 30, a BRS system 60, and an SFPCS system 100.
The “primary cooling system desalting apparatus” includes the mixed bed type desalting tower 33 of the CVCS system 30, the boron removal desalting tower 37, the mixed bed type desalting tower 62 of the BRS system 60, and the SFPCS system 100 in this embodiment. This is a mixed bed desalting tower 110. The “purifying means” means a packed bed of porous anion exchange resin in a primary cooling system desalting apparatus.

(Primary cooling water circulation line)
The primary cooling water circulation line 10 supplies heat generated in the nuclear reactor 12 as a heat source for the steam generator 14 via the primary cooling water. The primary coolant circulation line 10 includes a nuclear reactor 12, a steam generator 14, a primary coolant pump 16, a regenerative heat exchanger 18, and pipes 20, 21, 22, and 24. The nuclear reactor 12 is connected to the steam generator 14 by a pipe 20, the steam generator 14 is connected to a primary cooling water pump 16 by a pipe 21, and the primary cooling water pump 16 is connected to the nuclear reactor 12 by a pipe 22. . The pipe 24 branched from the branch 23 of the pipe 21 is connected to the regenerative heat exchanger 18.

As the nuclear reactor 12, a nuclear reactor normally used in a PWR type power plant can be used.
The steam generator 14 is a device that uses the primary cooling water that has become high temperature and high pressure in the nuclear reactor 12 as a heat medium, and generates water vapor by heat exchange with the secondary cooling water.
The regenerative heat exchanger 18 is a device that performs heat exchange between the primary cooling water that has been heat-exchanged by the steam generator 14 and the primary cooling water that is supplied from the CVCS system 30.

(Chemical volume control system: CVCS system)
The CVCS system 30 purifies primary cooling water by removing fission products and corrosion products in the primary cooling system 8 and adjusts the amount of primary cooling water, boron concentration, and corrosion inhibitor. The CVCS system 30 includes a non-regenerative cooler 31, a mixed bed type desalting tower inlet filter 32, a mixed bed type desalting tower 33, a cation desalting tower 35, a boron removing desalting tower 37, and cooling water. Filter 38, volume control tank 39, pure water tank 80, chemical tank 82, piping 40, 41, 43, 44, 46, 47, 49, 50, 51, 53, 55, 57, 58, 81, 83 and valves 34 and 36.
The regenerative heat exchanger 18 and the non-regenerative heat exchanger 31 are connected by a pipe 40. The non-regenerative heat exchanger 31 and the mixed bed type demineralization tower inlet filter 32 are connected by a pipe 41. The pipe 41 branches into a pipe 51 at a branch 42, and the pipe 51 is connected to the cooling water filter 38. The mixed bed type desalting tower inlet filter 32 and the mixed bed type desalting tower 33 are connected by a pipe 43, and the pipe 44 connected to the mixed bed type desalting tower 33 is connected to a pipe 51 by a branch 52. Yes. The pipe 44 is branched into a pipe 46 at a branch 45, and the pipe 46 is connected to the cation demineralization tower 35 via a valve 34. A pipe 47 is connected to the cation demineralization tower 35, and the pipe 47 is connected to the pipe 44. The pipe 44 is branched into a pipe 49 at a branch 48, and the pipe 49 is connected to a boron removal desalting tower 37 via a valve 36. A pipe 50 is connected to the boron removal desalting tower 37, and the pipe 50 is connected to the pipe 44.
The cooling water filter 38 and the volume control tank 39 are connected by a pipe 53. In the pipe 53, a pipe 70 is branched at a branch 54. A pipe 55 branched from a branch 56 of the pipe 58 is connected to the pipe 53. The volume control tank 39 is connected to the regenerative heat exchanger 18 by a pipe 57. A pipe 81 of a pure water tank 80 is connected to the pipe 58. A pipe 83 of the chemical tank 82 is connected to the pipe 57.

The non-regenerative cooler 31 is a device that further reduces the temperature of the primary cooling water that has passed through the regenerative heat exchanger 18.
The mixed bed type desalting tower inlet filter 32 is a device for removing components such as fine particles that cannot be removed by an ion exchange resin, and examples thereof include a pleated filter using a polypropylene nonwoven fabric.

The mixed bed desalting tower 33 is used for impurities such as chloride ions and fluoride ions in the primary cooling water, fission products such as ¹³¹ I, and corrosion products such as ⁵⁸ Co, ⁶⁰ Co, nickel, and iron. It is a device that performs the removal. The mixed bed desalting tower 33 is filled with an ion exchange resin obtained by mixing an anion exchange resin and a cation exchange resin.
The structure of the anion exchange resin packed in the mixed bed type desalting tower 33 may be porous or macroporous (MR) as long as it is porous. By using the porous shape, cracks and cracks due to contact with high concentration boric acid can be prevented.
The pore volume of the porous anion exchange resin is 0.05 to 0.50 mL / g-dry resin (Cl form) and 0.25 to 0.45 mL / g-dry resin (Cl form). Is preferred. When the pore volume is less than 0.05 mL / g-dry resin (Cl form), the porous anion exchange resin may be cracked or cracked when boric acid is brought into contact therewith. It is because load strength will fall when it exceeds 0.50 mL / g-dry resin (Cl form).
The average pore radius of the porous anion exchange resin is preferably 2 to 50 nm (Cl type), and more preferably 5 to 30 nm (Cl type). If it is less than 2 nm (Cl type), the porous anion exchange resin may be cracked or cracked when boric acid is brought into contact therewith. This is because if it exceeds 50 nm (Cl form), the ion exchange capacity decreases.

Here, the pore volume and the average pore radius are determined by the following measuring method.
A 15 mL of anion exchange resin is brought into contact with an aqueous hydrochloric acid solution (1 mol / L) at 9 to 10 mL / min to obtain a chloride ion form. Then, it substitutes in order of methanol, toluene, and isooctane, and it is made to dry at 60 degreeC for 8 hours using a vacuum dryer. The dried anion exchange resin is placed in a measurement cell, filled with mercury, and the inside of the cell is pressurized to allow mercury to enter the pores. The pressure and mercury intrusion amount at this time are measured to determine the pore volume. Further, assuming that the pore is cylindrical, the pore radius is obtained. The relationship between the applied pressure and the pore diameter through which mercury can enter at that pressure is expressed by the following equation (1) (Washburn's equation). Examples of the measuring device for the pore volume and the average pore radius include a mercury porosimeter (Autopore IV9520, manufactured by Shimadzu Corporation).

−4σ cos θ = PD (1)
σ: Surface tension of mercury (0.475 N / m)
θ: Contact angle (140 °)
D: pore diameter (m)
P: Pressure (Pa)

The anion exchange resin may be a strong base anion exchange resin or a weak base anion exchange resin, but is preferably a strong base anion exchange resin.
Examples of such porous anion exchange resins include Amberlite (trade name) IRA900, AmberJet (trade name) 9090 (above, manufactured by Rohm and Haas).

The cation exchange resin packed in the mixed bed desalting tower 33 is a cation exchange resin having an ion form of ⁷ Li. The structure of the Li-type cation exchange resin is not particularly limited, and may be a gel type or a porous type. Moreover, although it may be a strong acid cation exchange resin or a weak acid cation exchange resin, it is preferably a strong acid cation exchange resin.
The mixing ratio of the anion exchange resin and the cation exchange resin in the mixed bed type desalting tower 33 is not particularly limited, but the anion exchange resin and the cation exchange resin are set to have an ion exchange capacity ratio of 1: 1. It is preferable.

  The cation desalting tower 35 is an apparatus mainly intended for controlling the lithium concentration in the primary cooling water and reducing the cesium concentration that is difficult to remove by the mixed bed desalting tower 33. The cation desalting tower 35 is filled with a cation exchange resin. The cation exchange resin packed in the cation desalting tower 35 is an H-type cation exchange resin.

  The boron removal desalting tower 37 is an apparatus that mainly removes boric acid in the primary cooling water to adjust the concentration. The boron removal desalting tower 37 is filled with a porous anion exchange resin. The anion exchange resin packed in the boron removal desalting tower 37 is the same as the anion exchange resin packed in the mixed bed desalting tower 33.

The cooling water filter 38 removes suspensions such as metal corrosion products that cannot be removed by the ion exchange resin, and fine particles leaked from the mixed bed desalting tower 33, the cation desalting tower 35, and the boron removing desalting tower 37. It is a device to do. The cooling water filter 38 is the same as the mixed bed type desalting tower inlet filter 32.
The volume control tank 39 is not particularly limited, and a tank used in a normal PWR type power plant can be used.

  The pure water tank 80 stores pure water used for primary cooling water. The chemical tank 82 is used for addition of lithium for adjusting the pH of the primary cooling water, addition of hydrazine for removing oxygen at start-up, and addition of hydrogen peroxide at the time of stop.

(Boric acid recovery system: BRS system)
The BRS system 60 separates and recovers boric acid in the primary cooling water and reuses it. The BRS system 60 includes a cooling water storage tank 61, a mixed bed type desalting tower 62, a cooling water filter 63, a boric acid recovery device 64, a cooler 65, a mixed bed type desalting tower 66, and boric acid. The tank 67, the boric acid filter 68, and pipes 70, 71, 72, 73, 74, 76, 77 are configured.

  A pipe 70 branched from a branch 54 of the pipe 53 of the CVCS system 30 is connected to a cooling water storage tank 61. The cooling water storage tank 61 and the mixed bed type desalting tower 62 are connected by a pipe 71, and the mixed bed type desalting tower 62 and the cooling water filter 63 are connected by a pipe 72, and the cooling water filter 63 and the boric acid recovery device are connected. 64 is connected by a pipe 73. A piping 74 and a piping 76 are connected to the boric acid recovery device 64. The pipe 74 is connected to the mixed bed desalting tower 66 via the cooler 65. The piping 76 is connected to the boric acid tank 67, and the boric acid tank 67 and the boric acid filter 68 are connected by a piping 77. The boric acid filter 68 is connected to the pipe 57 by a pipe 58.

The mixed bed desalting tower 62 is the same as the mixed bed desalting tower 33.
The cooling water filter 63 is a device that removes components such as fine particles that cannot be removed by an ion exchange resin, and is the same as the mixed bed type desalting tower inlet filter 32.

The boric acid recovery device 64 is a device that concentrates boric acid in the primary cooling water and separates it into a boric acid concentrate and water.
The cooler 65 is a device that condenses the water separated by the boric acid recovery device 64.
The mixed bed desalting tower 66 is a device that removes and purifies the water separated by the boric acid recovery device 64. The structure of the anion exchange resin packed in the mixed bed type desalting tower 66 is not particularly limited, and may be a gel type or a porous type. Further, the type of anion exchange resin may be a strong basic anion exchange resin or a weak basic anion exchange resin. The cation exchange resin charged in the mixed bed desalting apparatus 66 is not particularly limited, and the same cation exchange resin as that used in the mixed bed desalting tower 33 can be used.
The boric acid filter 68 is a device that removes fine particles contained in the boric acid concentrate.

(Spent fuel pit water purification cooling system: SFPCS system)
The SFPCS system 100 is a system that performs decay heat removal of spent fuel stored in a pit and purifies pit water. The SFPCS system 100 includes a fuel pit 104, a mixed bed type desalting tower 110, a spent fuel pit filter 111, a cooler 112, and pipes 120, 122, 123, 124, and 125.

The fuel pit 104 includes a reactor well 101, a partition wall 103, and a spent fuel pit 102. Primary cooling water is stored in the reactor well 101 and the spent fuel pit 102.
A reactor well 101 is installed in the upper part of the reactor 12, and a spent fuel pit 102 is installed through the reactor well 101 and the partition wall 103. The spent fuel pit 102 and the cooler 112 are connected by a pipe 120. The cooler 112 is connected to the pipe 124 by a pipe 125. The pipe 120 branches into a pipe 122 at a branch 121, and the pipe 122 is connected to the mixed bed type desalting tower 110. The mixed bed desalting tower 110 and the spent fuel pit filter 111 are connected by a pipe 123. A pipe 124 is connected to the spent fuel pit filter 111, and the pipe 124 is connected to the spent fuel pit 102.

The fuel pit 104 is not particularly limited, and a fuel pit 104 that is normally used in a PWR type power plant can be used.
The mixed bed desalting tower 110 is the same as the mixed bed desalting tower 33.
The spent fuel pit filter 111 is a device that removes components such as fine particles that cannot be removed by an ion exchange resin, and is the same as the mixed bed type desalting tower inlet filter 32.
The cooler 112 removes decay heat generated by the spent fuel.

Hereinafter, the purification method of the primary cooling water will be described.
In the present invention, “purification” refers to corrosion of impurities such as chloride ions and fluoride ions, fission products such as ¹³¹ I, and ⁵⁸ Co, ⁶⁰ Co, nickel, iron, and the like from primary cooling water. Say to remove the product.
The primary cooling water is circulated in the primary cooling water circulation line 10 by the primary cooling water pump 16. The primary cooling water cools the reactor 12 and becomes high temperature and high pressure (for example, temperature 322 ° C., pressure 15.4 MPa). The primary cooling water having a high temperature and a high pressure is sent to the steam generator 14 via the pipe 20. The primary cooling water sent to the steam generator 14 generates steam for power generation through heat exchange with the secondary cooling water via the heat exchanger of the steam generator 14. The primary cooling water heat-exchanged by the steam generator 14 is sent to the primary cooling water pump 16 via the pipe 21 and reaches the nuclear reactor 12 via the piping 22 from the primary cooling water pump 16. On the other hand, a part of the primary cooling water exchanged by the steam generator 14 is sent from the branch 23 of the pipe 21 to the regenerative heat exchanger 18 via the pipe 24. The primary cooling water that has passed through the pipe 24 sent to the regenerative heat exchanger 18 is subjected to heat exchange with the primary cooling water sent from the CVCS system 30 and then sent to the non-regenerative heat exchanger 31.

  Next, the primary cooling water cooled by the non-regenerative heat exchanger 31 with the valves 34 and 36 closed is mixed with the pipe 41, the mixed bed type demineralization tower inlet filter 32, and the pipe 43. It is sent to the floor type desalting tower 33. The primary cooling water comes into contact with the porous anion exchange resin in the mixed bed desalting tower 33, and anions such as chloride ions, fluoride ions and sulfate ions are removed. Further, in contact with the cation exchange resin, cations such as nickel ions, iron ions and cobalt ions are removed. Thereafter, the primary cooling water reaches the pipe 51 at the branch 52 via the pipe 44.

  When adjusting the lithium concentration and cesium concentration in the primary cooling water, the valve 34 is opened, the valve 36 is closed, and the primary cooling water that has circulated through the mixed bed demineralization tower 33 is circulated to the cation demineralization tower 35. Let Further, when reducing the boron concentration in the primary cooling water, such as when restarting from the shutdown of the PWR type power plant, the valve 36 is opened and the boron removal and desalting tower 37 is circulated so that boric acid in the primary cooling water is circulated. Remove. In this way, the primary cooling water is purified.

  The purified primary cooling water is stored in the volume control tank 39 through the pipe 44, the branch 52, the pipe 51, the cooling water filter 38, and the pipe 53 in this order. The primary cooling water stored in the volume control tank 39 is supplied with chemicals from the chemical tank 82 so as to have an arbitrary chemical concentration, and is recovered by pure water in the pure water tank 80 and the BRS system 60. The supply of boric acid is received and the primary cooling water circulation line 10 is reached via the pipe 57 and the regenerative heat exchanger 18 (the CVCS system 30).

  A part of the primary cooling water from which fission products, corrosion products, and the like are removed is stored in the cooling water storage tank 61 from the branch 54 of the pipe 53 via the pipe 70. The primary cooling water of the cooling water storage tank 61 flows through the mixed bed type desalting tower 62 via the pipe 71. During this time, fission products, corrosion products, etc. in the primary cooling water are further removed. Thereafter, the solution is sent to the boric acid recovery device 64 via the pipe 72, the cooling water filter 63, and the pipe 73. The boric acid concentrate concentrated by the boric acid recovery device 64 is stored in the boric acid tank 67 via the pipe 76. Thereafter, the water is appropriately diluted with pure water in the pure water tank 80 via the pipe 77, the boric acid filter 68, and the pipe 58, and reaches the pipe 57. A part of the boric acid concentrate diluted with pure water is sent from the branch 56 of the pipe 58 to the primary side of the volume control tank 39 via the pipe 55. On the other hand, the water separated by the boric acid recovery device 64 flows through the mixed bed type desalting tower 66 through the pipe 74 and the cooler 65, and is further purified (hereinafter referred to as the BRS system 60).

  The spent fuel in the reactor 12 is taken out from the reactor 12 to the reactor well 101, the partition wall 103 of the fuel pit 104 is opened, and the fuel is transferred from the reactor well 101 to the spent fuel pit 102. The spent fuel is immersed in the primary cooling water in the spent fuel pit 102. The primary cooling water of the spent fuel pit 102 is sent to the cooler 112 through the pipe 120, cooled, and then sent to the spent fuel pit 102 via the pipes 125 and 124. A part of the primary cooling water is sent to the mixed bed desalting tower 110 via the pipe 120, the branch 121, and the pipe 122 and purified. Then, it is sent to the spent fuel pit 102 via the pipe 123, the spent fuel pit filter 111, and the pipe 124. Thus, the purified and cooled primary cooling water is supplied to the spent fuel pit 102 (the SFPCS system 100).

  The boron concentration of the primary cooling water that is brought into contact with the boric acid type anion exchange resin in the demineralizer of the primary cooling system 8 is not particularly limited, and is operated in the range of, for example, 500 to 10,000 ppm. The present invention is more effective when operated at a boron concentration of 3000 ppm or higher, and particularly effective when operated at a boron concentration of 3500 ppm or higher.

  As described above, by using a porous anion exchange resin for the desalination apparatus of the primary cooling system 8, even if a high-concentration boric acid solution is brought into contact with the anion exchange resin, the anion exchange resin is broken or broken. Does not occur. For this reason, the leakage of the anion exchange resin-derived particles from the desalting apparatus can be extremely reduced, and it is possible to prevent the filter or the like installed at the subsequent stage of each desalting apparatus from being blocked at an early stage. In the conventional gel-type anion exchange resin, when a high concentration boric acid solution is brought into contact, the resin withstands the volume change because the resin contracts rapidly due to the ionic shape change and osmotic pressure difference. It is thought that cracks and cracks occur. On the other hand, since the porous resin is buffered by the pores of the resin at the time of rapid contraction, it is considered that generation of cracks and cracks can be prevented.

  In the primary cooling system 8 described above, all of the demineralizers of the mixed bed type desalting tower 33, the boron removing desalting tower 37, the mixed bed type desalting tower 62, and the mixed bed type desalting tower 110 have porous anions. The exchange resin is filled. However, the present invention is not limited to this, and a part of each desalting apparatus may be filled with a porous anion exchange resin.

EXAMPLES Hereinafter, although an Example is given and this invention is demonstrated concretely, it is not limited to an Example.
(Example 1)
Amberjet (trade name) 9090 which is a porous anion exchange resin (pore volume: 0.16 mL / g-dry resin (Cl form), average pore radius: 17 nm (Cl form), Rohm and Haas Product) was measured (damage rate before water flow). Next, 15 mL of amber jet (trade name) 9090 was packed in a glass column having an inner diameter of 21 mm, and an anion exchange tower A was produced. 4700 ppm boric acid aqueous solution as boron was passed through the obtained anion exchange tower A at SV (space velocity) = 20 for 1 hour. After passing water, the porous anion exchange resin A was taken out and the damage rate of the resin was measured (damage rate after passing water). Table 1 shows the measurement results.

(Comparative Example 1)
Resin before passing water in the same manner as in Example 1 except that the anion exchange resin was Amberlite (trade name) PCA1 (manufactured by Rohm and Haas), which is an OH gel anion exchange resin. The breakage rate of the resin and the breakage rate of the resin after water flow were measured. Table 1 shows the measurement results.

(Comparative Example 2)
Damage to the resin before passing water in the same manner as in Example 1 except that Diaion (trade name) SAN1 (manufactured by Mitsubishi Chemical Corporation), which is an OH gel anion exchange resin, was used as the anion exchange resin. The rate and the failure rate of the resin after water flow were measured. Table 1 shows the measurement results.

(Measurement of damage rate)
300 arbitrary resins were observed with a microscope (25 times), and the number of broken resins in which breakage such as cracks and cracks occurred was measured. The breakage rate was expressed as a percentage determined by the following equation (2).
Damage rate (%) = number of damaged resins / 300 × 100% (2)

  As shown in Table 1, in Example 1 using the porous anion exchange resin, the breakage rate before passing water and the breakage rate after passing water were less than 1%. On the other hand, in Comparative Example 1 and Comparative Example 2 using the OH-type gel-type anion exchange resin, the breakage rate before passing water was less than 1%, whereas the breakage rate after passing water was lower. It was over 20%. From this, it was found that the porous anion exchange resin is hardly damaged by contact with boric acid.

It is a schematic diagram which shows the primary cooling system of the PWR type | mold power plant which is an example of embodiment of this invention.

Explanation of symbols

8 Primary cooling system 30 Chemical volume control system 33, 62, 110 Mixed bed type desalting tower 37 Boron removal desalting tower 60 Boric acid recovery system 100 Spent fuel pit water purification cooling system

Claims (3)

A desalinator for purifying primary cooling water of a pressurized water nuclear power plant,
Purifying means filled with a porous anion exchange resin having a pore volume of 0.05 to 0.50 mL / g-dry resin (Cl type) and an average pore radius of 2 to 50 nm (Cl type) A desalination system for a primary cooling system of a pressurized water nuclear power plant.   The desalination apparatus for a primary cooling system according to claim 1, wherein the desalination apparatus is disposed in at least one of a chemical volume control system, a boric acid recovery system, and a spent fuel pit water purification cooling system.   A porous anion exchange resin having a pore volume of 0.05 to 0.50 mL / g-dry resin (Cl type) and an average pore radius of 2 to 50 nm (Cl type) is added to a pressurized water nuclear power plant. A method for purifying primary cooling water of a pressurized water nuclear power plant, in which primary cooling water is contacted.

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