JPH0315800A - Reactor auxiliary cooling system equipment for atomic power plant - Google Patents

Abstract

PURPOSE:To prevent freezing of the coil of a warming air conditioner of an intra-reactor hot water system by leading cooling water of an RCW (reactor auxiliary cooling system) to an intra-reactor hot water system heat exchanger at the time of stopping a CUW (reactor refrigerant purifying system) circulating pump. CONSTITUTION:In the RCW, the waste heat for cooling of a reactor refrigerant purifying system non-regenerative heat exchanger is used to heat the warming air conditioner of the intra-reactor hot water system. A by-pass line 20 is provided on the duct between a CUW non-regenerative heat exchanger 7 and an intra-reactor hot water system heat exchanger 8 to by-pass a temperature control valve 12. Since the diameter of piping of this line is set to a desired value, cooling water at about 30 deg.C flowing in the RCW is supplied to the exchanger 8 through the line 20 even if a CUW circulating pump 14 is stopped to completely close the control valve 12. Consequently, the reduction of the hot water temperature in the intra-reactor hot water system is prevented to prevent freezing of the coil of the warming air conditioner.

Description

[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) This invention relates to a reactor auxiliary cooling system of a nuclear power plant that cools reactor coolant cleaning system (hereinafter referred to as CUW) equipment. (hereinafter referred to as RCW) equipment.

(Conventional technology) The RCW of a nuclear power plant consists of emergency equipment that functions in the event of a reactor accident, etc., and regular I that functions during normal reactor operation.
FF unit and the FF unit, respectively.

FIG. 5 is a system diagram showing a conventional RCW facility. R.C.
The W equipment cools the cooling water pressurized by the cooling water bomb 1 through the seawater heat exchanger 2 with the seawater pressurized by the seawater pump 3, and then transfers this cooling water to the emergency m equipment 4, C ( It is supplied to the JW circulation pump cooler 6, CUW non-regenerative heat exchanger 7, etc. Also, the waste heat from the CUW non-regenerative heat exchanger 7 is recovered and sent to the heating air W4119 (see Figure 16) of the in-house hot water system. For the purpose of supplying heat, an in-house hot water heat exchanger 8 is installed downstream of the CLIW non-regenerative heat exchanger 7.

In addition, the RCW equipment is equipped with regular/emergency separation valves 9 and 10.11, which stop the supply of cooling water to the regular equipment 5, etc. in the event of an emergency, and supply sufficient chilled water to the emergency equipment 4. It is supposed to be done.

Furthermore, a temperature W4 regulating valve 12 is disposed between the CLIW non-regenerative heat exchanger 7 and the station hot water system heat exchanger 8, etc., so that the CUW system reactor water immediately cooled by the CUW non-regenerative heat exchanger 7 is The temperature is kept constant.

FIG. 6 is a system diagram of conventional CUW equipment and in-house hot water system equipment.

The reactor coolant is purified by supplying the coolant (reactor water) from the reactor 13 to the CUW regenerative heat exchanger 15, CUW non-regenerative heat exchanger 7, and filtration chlorination device 16 through the CUW circulation bomb 14. are doing. Here, the CUW non-regenerative heat exchanger 7 is operated by the cooling water 17 of the RCW equipment.
The reactor water is cooled to a temperature at which the filtration and demineralization device 16 can operate.

Further, the knitting adjustment valve 12 is installed on the cooling water outlet side of the CUW non-regenerative heat exchanger 7, and the in-house water purification system heat exchanger 8 is installed further downstream thereof.

This in-house edited water system heat exchanger 8 is a CUW non-regenerative heat exchanger 7.
The hot water heated by the waste heat recovered from the water is pressurized by the in-house water pump 18 and used for heating air conditioning! Supply to ill9.

(Problem that R-ming is trying to solve) In conventional RCW equipment, when the CUW circulation bomb 14 shown in FIG. 6 stops, the RCW temperature control valve 12 (FIGS. 5 and 6) is fully opened. In-house lagoon water heat exchanger 8
The supply of cooling water 17 to is cut off. As a result, the temperature of the station hot water system decreases, and there is a risk that the coil in the heating air conditioner 19 of the station hot water system may freeze in winter.

This invention was made in consideration of the above circumstances,
Even if the CUW circulation bomb stops in the winter and the in-house water leakage heat exchanger cannot utilize the waste heat from the CUW non-regenerative heat exchanger, the coils of the in-house hot water system's heating air conditioner can be prevented from freezing. The purpose is to provide ROW equipment for nuclear power plants.

(Structure of the Invention) (Means for Solving the Problems) This invention supplies cold water to regular equipment, emergency Ia equipment, CUW non-regenerative heat exchangers, etc.
At the same time, the cooling water cooled by the CUW non-regenerative heat exchanger is guided to the in-house hot water system heat exchanger of the in-house hot water system, and the CUW non-regenerative heat exchanger 3! In the RCW equipment of a nuclear power plant that uses waste heat from the J8 unit to heat the heating air conditioner of the above-mentioned station hot water system, even when the CUW circulation pump of the CUW is stopped, the above-mentioned cooling water flowing through the RCW is used to heat the above-mentioned station hot water system. It is characterized by the fact that it is designed to lead to the W4 vessel.

(Function) Generally, the temperature of the cooling water flowing through the RCW is around 30°C. Therefore, when the CUW circulation pump is stopped, the RCW
When the cooling water flowing through the station is guided to the station hot water system heat exchanger, the temperature of the hot water flowing through the station hot water system is prevented from decreasing, and the coil of the heating air conditioner of the station hot water system can be prevented from freezing.

(Practical example) Hereinafter, a practical example according to the present invention will be described based on the drawings.

FIG. 1 shows the RCW of the nuclear power plant according to the present invention.
It is a system diagram showing a first example of equipment.

In this first embodiment, the same parts as those in the conventional example are given the same arrows and the explanation will be omitted.

A bypass line 20 is installed in the pipeline between the CUW non-regenerative heat exchanger 7 and the in-house hot water heat exchanger 8 in RCWk:l3 so as to bypass the temperature control valve 12. The piping diameter of this bypass line 20 is such that when the CUW circulation pump 14 is stopped and the RCW temperature control valve 12 is fully opened, the cooling water of about 30° of the RCW is frozen in the coil of the heating air conditioner Il 19. The diameter is set to be able to supply only the necessary flow rate to prevent this.

In the unlikely event that CUW* ring bomb 14 stops, R
Even if the temperature control valve 12 of the CW is fully closed, the cooling water flowing through the RCW after about 30'Cyr is supplied to the in-house hot water system heat exchanger 8 via the bypass line 20. Therefore, it is possible to prevent the temperature of the hot water in the in-house hot water system from decreasing, and as a result, the coil of the heating air conditioner 19 can be prevented from freezing.

This will be explained in detail with reference to FIG. FIG. 4 is a graph showing the relationship between the flow rate ratio of the RCW cooling water 17 supplied to the station hot water system heat exchanger 8 via the bypass line 20 and the hot water temperature of the station hot water system. The horizontal axis in this graph indicates the flow rate ratio of the RCW cooling water 17 supplied to the in-house hot water system heat exchanger 8, and the flow rate ratio of 1.0 is the design flow rate of the in-house hot water system heat exchanger 8. The vertical axis shows the temperature of the hot water in the lagoon water system. The solid line in FIG. 4 indicates the outlet temperature of the station hot water system heat exchanger 8 {the inlet temperature of the heating air conditioner 19}, and the broken line indicates the inlet temperature of the exchanger 8 (the outlet temperature of the heating air conditioner 19). .

The inlet knitting temperature of the in-house hot water system heat exchanger 8 (the outlet temperature of the heating air conditioner 19) is approximately 30 mm, which is supplied to the in-house hot water system heat exchanger 8
When the flow rate ratio of the RCW cooling water 17 of °C is changed, the flow rate ratio of the chilled water drops below 0 °C around about 0.5, and the coil of the heating air conditioner 19 freezes. Therefore, by setting the flow ratio of the cooling water 17 of the ROW to 0.5 or more, freezing of the coils of the heating air 14 machine 19 can be prevented.

Note that the flow rate ratio of the RCW cooling water 17 for preventing freezing is determined for each R lightning station because the outside air temperature, the configuration of the air conditioning equipment, etc. are different for each power station.

FIGS. 2 and 3 are system diagrams respectively showing 2J5 and 3rd embodiments of RCW equipment for a nuclear power plant according to the present invention. In these second and third embodiments, the same parts as in the first embodiment are designated by the same reference numerals, and a description thereof will be omitted.

In the second embodiment shown in FIG. 2, a bypass line 21 is provided in the RCW pipe line, bypassing the temperature control valve 12 and the CUW non-regenerative heat exchanger 7.
A bypass valve 22 is installed at 1. This bypass valve 22
is automatically opened in the event that the temperature control valve 12 is completely closed.

In the third embodiment shown in FIG. 3, the temperature of the first embodiment is J4.
A temperature control valve 23 with a leap direction lock is installed in place of the control valve 12. This temperature control valve 23 is constructed by installing a stopper in the closing direction on the temperature control valve 12 to prevent the valve from being fully closed. In these second and third storage examples, C
When the UW circulation pump 14 is stopped, the RCW cold water 1γ can be supplied to the in-house hot water system heat exchanger 8, and the coil of the heating air conditioner i19 can be prevented from freezing.

[Effects of the invention] As described above, the R of the nuclear power plant according to this invention is
According to the CW equipment, even when the CLIW circulation pump of the CUW is stopped, the cooling water flowing through the RCW is guided to the in-house hot water system heat exchanger, which prevents a drop in the temperature of the hot water flowing through the in-house hot water system, thereby preventing heating of the in-house hot water system. Prevents the coils of commercial air conditioners from freezing.

[Brief explanation of the drawing]

FIG. 1 is a system diagram showing a first embodiment of RCW equipment for a nuclear power plant according to the present invention, and FIGS. 2 and 3 are system diagrams showing second and third embodiments of the invention, respectively.
Fig. 4 is a graph showing the relationship between the RCW cooling water flow rate ratio and the hot water temperature of the in-house hot water system in the first embodiment, Fig. 5 is a system diagram showing the conventional RCW equipment, and Fig. 6 is the conventional CUW and It is a system diagram showing an in-house hot water system. 4... Emergency equipment, 5... Regular use l! Equipment, 7...
Reactor coolant circulation system (CLJW) non-regenerative heat exchanger, 8.
... In-house hot water system heat exchanger, 12 ... Temperature control valve, 14
... Reactor cold material purification system (CUW) circulation bomb, 17
...Cooling water, 19...Heating air conditioner, 20...Bypass line.

Claims (1)

[Claims] Cooling water is supplied to regular equipment, emergency equipment, non-regenerative heat exchangers of the reactor coolant purification system, etc. to cool these equipment, and cooling water is supplied to cool the non-regenerative heat exchangers of the reactor coolant purification system. A nuclear power generation plant in which water is guided to the station hot water system heat exchanger of the station hot water system, and the waste heat from the non-regenerative heat exchanger of the reactor coolant purification system is used to heat the heating air conditioner of the station hot water system. In the reactor auxiliary cooling system equipment, the cooling water flowing through the reactor auxiliary cooling system is guided to the station hot water system heat exchanger even when the reactor coolant purification system circulation pump of the reactor coolant purification system is stopped. A reactor auxiliary cooling system equipment for a nuclear power plant characterized by being configured as follows.