JPH1037717A - Complex power generating facility - Google Patents

Abstract

PROBLEM TO BE SOLVED: To improve power generation efficiency safely without discharging radioactive fluid to the atmosphere. SOLUTION: At a nuclear power generating plant 1, a gas turbine generating plant 2 is installed in parallel. An exhaust heat recovery boiler 3 is connected to a gas turbine 15. In a heat transfer tube 29 in this boiler 3, an intermediate loop is provided for connecting the main steam heater the plant 1 and a low pressure water supply heater 25. This intermediate loop comprises an inflow side piping 31, a circulating pump 32, an outflow side piping 33 and a flow channel pipings 36 and 37. As an operation fluid of the intermediate loop, either pure water, nitride molten salt or a liquid metal is used to take out heat from the boiler 3 and the output steam from the nuclear reactor 4 is heated to a high temperature. In this manner, the exhaust heat of the gas turbine power generating plant 2 is utilized in the nuclear power generating plant 1, so that a temperature difference becomes larger as an superheated heat source and the power generating efficiency is remarkably improved.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear power plant using light water as a coolant, and a combined cycle power plant equipped with a gas turbine cycle as a topping cycle or a low-boiling medium cycle as a bottoming cycle.

[0002]

2. Description of the Related Art The concept of a combined power generation system combining nuclear power generation and gas turbine power generation is known. It is said that this combined power generation system can effectively utilize the steam of the reactor, greatly improve the thermal efficiency and increase the total output compared to the case where both power generations are performed separately.

Further, a combined gas and steam power generation facility provided with an exhaust heat recovery boiler between a gas turbine power generation plant and a gas turbine power generation plant attached to a nuclear power plant is disclosed in, for example, Japanese Patent Laid-Open No. 3-1515.
No. 05 discloses this. This combined power generation facility will be schematically described with reference to FIG.

[0004] That is, in FIG. 13, reference numeral 1 denotes a nuclear power plant, 2 denotes a gas turbine power plant attached to the nuclear power plant 1, and an exhaust heat recovery boiler 3 is provided between the nuclear power plant 1 and the gas turbine power plant 2. Is provided.

A nuclear power plant 1 is roughly divided into a reactor 4
And a steam turbine composed of a steam heater 5, a main steam pipe 6, a high-pressure turbine 7, and a low-pressure turbine 8 connected to the reactor 4, a generator 9 connected to the low-pressure turbine 8, and a steam turbine connected to the low-pressure turbine 8. A water supply unit 10 is provided with a water supply pipe 11 and a water supply pump 12 that connect between the condenser 10 and the nuclear reactor 4. The discharge side of the feed water pump 12 is connected to the economizer 13 in the exhaust heat recovery boiler 3 which operates in the same manner as the feed water heater.

[0006] The main steam heater 5 and the economizer 13 are incorporated in the exhaust heat recovery boiler 3. The gas turbine power plant 2 includes a combustion chamber 14, a compressor 16 disposed close to the combustion chamber 14, and a gas turbine 15 disposed on a common shaft with the compressor 16.
And a generator 17. The gas turbine 15 and the exhaust heat recovery boiler 3 are connected by a waste gas pipe 18. The air compressed by the compressor 16 flows into the combustion chamber 14 and the combustion chamber 14
The fuel required for the operation of the gas is a gaseous or liquid fuel.

The high-temperature gas generated in the combustion chamber 14 loads the gas turbine 15, the load on the gas turbine 15 is removed, and the high-temperature gas consumed on the pressure side flows through the exhaust heat recovery boiler 3 as waste gas. After heating the steam heater 5 and the economizer 13, it passes through the exhaust pipe 19 as a flue gas and passes through a chimney (not shown).
Emitted from the atmosphere.

[0008]

The combined power generation system combining nuclear power generation and gas turbine power generation is still in the structural stage, and has problems such as the system becoming complicated. Further, in the combined power generation facility of the nuclear power plant 1 and the gas turbine power plant 2 shown in FIG. 13, the steam flowing out of the reactor 4 is superheated by the exhaust heat recovery boiler 3 and introduced into the high pressure turbine 7. The feedwater condensed in the condenser 10 is pressurized by the feedwater pump 12, introduced into the exhaust heat recovery boiler 3, superheated, and sent to the reactor 4.

However, when the reactor 4 is of a boiling water type, a fluid such as steam and water containing radioactivity is introduced into the exhaust heat recovery boiler, so that the exhaust heat recovery boiler 3 is set in the radiation control area. In addition, there are issues that require seismic design. In addition, if the heat transfer tube of the exhaust heat recovery boiler 3 is damaged, there is a safety problem such that radioactive gas is released into the atmosphere.

SUMMARY OF THE INVENTION The present invention has been made to solve the above problems, and solves the problem of seismic design without introducing a fluid containing radioactivity directly into an exhaust heat recovery boiler. An object of the present invention is to provide a combined power generation facility that is safe without releasing a fluid to the atmosphere, uses a waste heat of a gas turbine as a high superheat source, and can improve power generation efficiency.

[0011]

According to the first aspect of the present invention, a boiling water reactor using light water as a coolant, a main steam heater for superheating steam generated in the reactor, and a steam from the main steam heating are provided. It comprises a steam turbine that rotates as working steam and drives a generator, a condenser that condenses the exhaust of the steam turbine, a feedwater heater that feeds water to the reactor while heating the condensate of the condenser, and a feedwater pump. A nuclear power plant, a gas turbine power plant attached to the nuclear power plant, an exhaust heat recovery boiler connected to the gas turbine of the gas turbine power plant, and both ends of a heat transfer tube incorporated in the exhaust heat recovery boiler And an intermediate loop that connects the feed water heater and the main steam heater of the nuclear power plant by piping to form a circulation path.

[0012] The combined cycle power plant according to claim 1 is provided with an intermediate loop that mediates between the nuclear power plant and the gas turbine power plant, and the working fluid of the intermediate loop is at least one of pure water, nitrite-based dissolved salt and liquid metal. One type is selected and the heat of the exhaust heat recovery boiler is used effectively and safely to heat the steam at the reactor outlet. When using water as the working fluid,
The water in the intermediate loop is superheated by the waste heat recovery boiler, and the steam at the reactor outlet is heated by the main steam heater installed at the reactor outlet, so that the efficiency of the turbine cycle can be improved.

According to a second aspect of the present invention, the reactor includes a reactor control device for controlling a reactor outlet steam pressure, and the steam turbine detects a steam pressure state quantity from the reactor control device. A steam turbine control device having a detector and a steam control valve for receiving a signal from the steam pressure detector, wherein the gas turbine receives a steam temperature signal from a turbine inlet steam temperature signal from the steam turbine control device. A gas turbine control device having a detector and a fuel control valve connected to the steam temperature detector is provided.

The combined power generation control device according to the second aspect is for safely and efficiently controlling the combined power generation equipment according to the first aspect, and gives priority to the control of the nuclear reactor. Reactor pressure constant control is first, and fluctuations in reactor pressure due to disturbances are absorbed by opening and closing the steam control valve of the steam turbine. The steam turbine inlet temperature control is important for turbine protection, and the fuel injection amount of the gas turbine is controlled by a measured value of the inlet steam temperature so as to be controlled within a predetermined range.

The invention according to claim 3 is characterized in that the working fluid of the intermediate loop is made of pure water or cooling water whose pH is adjusted to 8.5 to 9.5. The pure water used in the present invention is easy to handle the working medium in the intermediate loop and has a pH of 8.5.
Cooling water adjusted to 9.5 has excellent coexistence from the viewpoint of material corrosion.

According to a fourth aspect of the present invention, a dissolved salt supply tank is provided at the inlet side of the waste heat recovery boiler in the intermediate loop, and the working fluid of the intermediate loop is made of a dissolved salt, a nitrite-based dissolved salt, or a liquid metal. It is characterized by.

The dissolved salt as the working fluid in the intermediate loop according to the fourth aspect has high chemical safety and is safe, so that the intermediate loop system can be maintained at a low pressure in a single phase, and the piping system and the like can be maintained. Design, production and operation are easier.
In addition, the nitrite-based dissolved salt exists as a liquid at a temperature range of 150 to 590 ° C, and is safe and safe, and has excellent properties as a heat transfer medium. Furthermore, liquid metal is in the temperature range
Exists as a liquid at 150-590 ° C and has excellent heat transfer properties.

The invention according to claim 5 is characterized in that a pressurizer is provided in the intermediate loop. According to the present invention, pure water or p in the intermediate loop is connected to the outlet pipe of the exhaust heat recovery boiler.
The working fluid such as cooling water whose H is adjusted is pressurized so that it does not boil and can be kept in a high pressure state, so that handling such as control of the working fluid in the intermediate loop becomes easy.

The invention according to claim 6 is characterized in that the intermediate loop is provided with an expansion tank for absorbing the volume expansion of the working fluid. According to the present invention, by installing the expansion tank in the intermediate loop, it is possible to absorb the volume expansion of the working fluid in the intermediate loop when starting up the combined power generator from room temperature in a stopped state to high temperature in a steady state. . As a result, it is possible to prevent generation of extra stress in the intermediate loop system.

According to a seventh aspect of the present invention, a stop valve is provided on each of the inflow side pipe and the outflow side pipe connected to the heat transfer pipe incorporated in the exhaust heat recovery boiler of the intermediate loop. According to the present invention, the stop valves are provided at the inlet and the outlet of the heat exchanger of the intermediate loop, and the nuclear power plant and the gas turbine plant are thermally separated by stopping the working fluid, so that they can be operated independently. . Therefore, when one power generation plant is stopped due to periodic inspection or the like, the other power generation plant can be operated independently.

According to an eighth aspect of the present invention, a first and a second circuit breaker are connected in parallel to the gas turbine generator, a system is connected in series to the first circuit breaker, and an atom is connected to the second circuit breaker. It is characterized in that furnace service systems are connected in series.

According to the invention of claim 8, leakage due to damage to the heat transfer tube can be prevented to a limited extent, and soundness can be maintained. Radioactive substances contained in the working fluid are not mixed into and leaked into the gas turbine power plant and the atmosphere.

According to a ninth aspect of the present invention, three gas turbine generators are arranged in parallel as first to third generators,
System, the reactor service system, and the first reactor emergency system are connected in parallel to each other via a circuit breaker, and the system system and the second emergency system are connected to the second gas turbine generator. Are connected in parallel via circuit breakers, respectively, and the system system and the third emergency system are connected in parallel to the third gas turbine generator via circuit breakers, respectively. For example, power can be supplied by arranging first to third gas turbine generators in parallel, connecting a system, a reactor service system, or a reactor emergency system to each gas turbine generator via a circuit breaker in series. The configuration is as follows. As a result, it is not necessary to provide an emergency power generator independently for the power supplies for the service system and the emergency system of the nuclear reactor as in the prior art, and it is possible to greatly simplify and reduce the cost.

According to the ninth aspect of the present invention, a gas turbine,
The electric power generated by the gas turbine generator is transmitted to the system via one circuit breaker. A part of this electric power is supplied through another circuit breaker as backup power for a normal electric power system of a nuclear reactor such as a reactor purification system and a condensate makeup water system. As a result, the load on the emergency generator can be significantly reduced.

According to a tenth aspect of the present invention, an auxiliary steam heater for feeding makeup water into the exhaust heat recovery boiler is incorporated, and the auxiliary steam for the nuclear power plant and the cooling and heating of the adjacent area are provided downstream of the auxiliary steam heater. It is characterized by connecting piping for equipment.

According to the tenth aspect of the present invention, the auxiliary steam heater is installed in the exhaust heat recovery boiler to heat the makeup water to generate the auxiliary steam. Auxiliary steam is required for nuclear power facilities, and can be used for cooling and heating in the plant and for heating and cooling loads in adjacent areas.

An eleventh aspect of the present invention provides a nuclear reactor, a main steam heater connected to the reactor via a main steam pipe, a high-pressure turbine connected to the main steam heater via a main steam pipe,
A generator connected to the high-pressure turbine, and an evaporator including a heat transfer tube into which steam flowing out of the high-pressure turbine flows,
A feed water heater connected via a pure water pump to a heat transfer tube outlet side in the evaporator, a feed water tube connecting the feed water heater and the reactor, and a heat transfer tube in the evaporator were heated. A gas-liquid separator into which low-boiling-point medium vapor flows, a low-pressure turbine rotated by the low-boiling-point medium vapor separated by the gas-liquid separator, a generator connected to the low-pressure turbine, and a low-pressure turbine flowing out of the low-pressure turbine. An absorber into which the boiling-point medium vapor flows, a condenser connected to the absorber, a regenerator connected to the condenser via a fluid pump, a return pipe connecting the regenerator and the evaporator, An intermediate loop pipe for discharging steam heated from the heat transfer pipe of the feed water heater, a economizer in an exhaust heat recovery boiler connected to the intermediate loop pipe via a booster pump, and an exhaust pipe connected to the economizer. Overheating in heat recovery boiler When, characterized by comprising an intermediate loop pipe connecting the said main steam heater this superheater and an intermediate loop pipe connecting the said feed water heater and the main steam heater.

According to the eleventh aspect of the present invention, there is provided a nuclear power plant in which only a high-pressure turbine is directly connected to a generator, a low-boiling-point medium power plant including a low-pressure turbine as a component, a gas turbine plant, an exhaust heat recovery boiler, and an intermediate loop. Construct a combined power generation facility. The plant efficiency can be further increased by setting the low-pressure turbine section to a low-boiling-point medium cycle.

A twelfth aspect of the present invention is characterized in that the low-boiling medium comprises a mixture of water and ammonia or Florinol 85. According to the present invention, it operates effectively and safely as a low-boiling-point medium, thereby contributing to an improvement in power generation efficiency of a plant.

According to a thirteenth aspect of the present invention, the heat transfer tubes of the main steam heater, the moisture separation heater, the feed water heater, and the evaporator which exchange heat with the intermediate loop have a metal braided body between the inner tube and the outer tube. It is characterized by having a double pipe structure inserted and attached. According to the present invention, it is possible to prevent the working fluid or the low boiling point medium from leaking from the heat transfer tube, and to detect the leak when the inner tube or the outer tube leaks, and to maintain the soundness of the heat transfer tube.

[0031]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a combined cycle power plant according to the present invention will be described with reference to FIG. In the drawing, the same portions or portions having the same functions as those in 13 are denoted by the same reference numerals. In FIG. 1, a nuclear power plant 1 includes a boiling water reactor 4 using light water as a coolant, a main steam pipe 6 for leading out steam generated in the reactor 4, and a downstream side of the main steam pipe 6. The main steam heater 20 is connected and this main steam heater 20
A high-pressure turbine 7 is connected via a main steam pipe 6 to the downstream side of the turbine. Two low pressure turbines 8 are coaxially connected adjacent to the high pressure turbine 7.

The steam rotating the high-pressure turbine 7 flows into the moisture separator / heater 21 and is heated by the heat transfer tube 34 thereof.
The steam flows through the steam pipe 22 and flows into the low-pressure turbine 8. The low-pressure turbine 8 rotates the generator 9 to generate power. The steam that has worked in the low-pressure turbine 8 flows into the condenser 10 to be condensed, and flows from the condenser pipe 23 to the heat transfer pipe 26 in the low-pressure feedwater heater 25 via the condenser pump 24.

The heat transfer pipe 26 is connected to the water supply pipe 11, and the heat transfer pipe 28 of the high pressure feed water heater 27 is connected to the water supply pipe 11.
Is connected to the reactor 4 by the water supply pipe 11, the feed water is heated by the high-pressure feed water heater 27 and flows into the reactor 4 through the water supply pipe 11.

On the other hand, the gas turbine power plant 2 comprises a gas turbine 15, a compressor 16 and a generator 17, and the exhaust heat side of the gas turbine 15 is connected to the exhaust heat recovery boiler 3.
The exhaust gas from the gas turbine 15 flows into the exhaust heat recovery boiler 3, and the exhaust gas that has heated the heat transfer tubes 29 in the exhaust heat recovery boiler 3 flows into the exhaust stack 30 and is released to the atmosphere.

An inlet pipe 31 of an intermediate loop is connected between the inlet side of the heat transfer pipe 29 and the low-pressure feedwater heater 25 via a circulation pump 32. The outlet pipe 33 of the intermediate loop is provided between the outlet side of the heat transfer pipe 29 and one end of the heat transfer pipe 35 in the main steam heater 20.
Is connected.

The other end of the heat transfer tube 35 in the main steam heater 20 and one end of the heat transfer tube 34 of the moisture separation heater 21 are connected by a flow pipe 36 of an intermediate loop. The other end of the heat pipe 34 and the high-pressure feed water heater 27 are connected by a flow path pipe 37 of an intermediate loop. The high-pressure feed water heater 27 and the low-pressure feed water heater 25 are connected by a flow path pipe 38 of an intermediate loop.

Thus, the inflow pipe 31, the circulation pump 32, the outflow pipe 33, and the flow pipes 36, 37, 38 are connected to the nuclear power plant 1 and the exhaust heat recovery boiler 3 via the heat transfer pipe 29. An intermediate loop of the circulation flow path through which the working medium flows is formed.

In this embodiment, the boiling water reactor 4
Is heated to 300-580 ° C. by the heat transfer pipe 35 of the main steam heater 20 with the working fluid from the outflow pipe 33 heated by the exhaust heat recovery boiler 3, and is introduced into the high pressure turbine 7. The steam that has worked in the high-pressure turbine 7 is a working fluid flowing through the flow pipe 36 and is supplied to the heat transfer pipe 34 of the moisture separation heater 21 by the heat transfer pipe 34.
It is heated to 350 ° C. and introduced into the low-pressure turbine 8.

The energy transmitted to the low-pressure turbine 8 is converted into electricity by the generator 9 and transmitted. After the work is completed, the steam is condensed in the condenser 10, pressurized by the condensate pump 24, heated by the low-pressure feedwater heater 25, the feedwater pump 12 and the high-pressure feedwater heater 27, and supplied to the reactor 4 as cooling water while being pressurized. You.

On the other hand, the heat transfer tube 29 in the exhaust heat recovery boiler 3
The gas turbine 15 has a function of efficiently transferring heat energy having a waste heat gas of about 600 ° C. to the working fluid of the intermediate loop. The intermediate loop is provided to isolate the gas turbine power plant 2 from radioactivity.

The working fluid flowing into the heat transfer pipe 27 in the waste heat recovery boiler 3 by the circulation pump 32 is heated from 460 to 590 ° C. by the waste heat gas of the gas turbine 15,
Through the main steam heater 20. The main steam heater 20 heats the outlet steam of the reactor 4 to 300 to 580 ° C.

The working fluid flowing out of the main steam heater 20 is guided to the moisture separation heater 21 and the outlet steam of the high-pressure turbine 7 is changed to 2.
The working fluid that has been heated to 50 to 350 ° C. and exited the moisture separator heater 21 is then led to a high pressure feedwater heater 27.

The high-pressure feed water heater 27 increases the reactor feed water from 190 to 2
The working fluid heated to 40 ° C. then reaches the low-pressure feedwater heater 25. The working fluid whose condensate is heated to 140 to 160 ° C. by the low pressure feed water heater 25 forms a closed group returning to the circulation pump 32.
According to the present embodiment, the efficiency of each power generation facility is 5 to 15
The power generation efficiency can be greatly improved overall.

Next, a second embodiment according to the present invention will be described with reference to FIG. FIG. 2 is a block diagram of a combined power generation control device according to the second embodiment of the present invention. The combined power generation control device of the present embodiment is based on the basics of comprehensive control including a reactor control device 39, a gas turbine control device 40, and a steam turbine control device 41.
For 41, a sufficiently reliable device has been put to practical use.

The main control of the present embodiment is the control of the reactor pressure of the nuclear reactor. The state value of the reactor outlet steam pressure 42 is detected by the pressure detector 43, and an opening / closing signal is sent to the steam control valve 44 of the steam turbine from the deviation from the set amount to perform a control operation. A feedback control 45 is performed by detecting a change in the state quantity of the reactor outlet steam pressure 42 due to the control operation, and stable reactor pressure constant control is performed.

The control of the steam temperature 46 at the inlet of the steam turbine is performed by the gas turbine controller 40. The state quantity of the steam temperature 46 at the inlet of the steam turbine is detected by a temperature detector 47, and an opening / closing signal is sent to a fuel control valve 48 of the gas turbine from a deviation from the set quantity to perform a control operation. A change in the state quantity of the steam turbine inlet steam temperature 46 accompanying the control operation is detected and feedback control is performed to perform stable inlet steam temperature constant control. As described above, the control of the combined cycle power generation equipment can be stably performed.

An example in which the pressure of the working fluid in the intermediate loop is set higher than the reactor steam pressure will be described. By using pure water as a working fluid and adopting a configuration as shown in FIG. 1 or FIG. 3 to be described later, a main steam heater 20 for exchanging heat with reactor steam or cooling water, a moisture separation heater 21, a high-pressure water supply In the heater 27 and the low-pressure feedwater heater 25, the pressure of the working fluid in the intermediate loop can be set higher than the pressure of the working fluid in the nuclear power plant.

In this way, even in the event of leakage from the heat transfer tube or pipe in the high pressure feed water heater 27, the main steam heater 20, and the moisture separation heater 21, the fluid containing radioactivity is prevented from entering the intermediate loop. Can be prevented.

Next, a third embodiment according to the present invention will be described with reference to FIG. In FIG. 3, the same portions as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping portions will be omitted.
This embodiment differs from the first embodiment in FIG. 1 in that a main steam heating pipe 5 and a economizer 13 are provided instead of the heat transfer pipe 29 in the exhaust heat recovery boiler 3 in FIG. That is, a booster pump 49 is provided between the inlet side of 13 and the inflow pipe 31 of the intermediate loop, and a steam reservoir 50 is provided between the main steam heating pipe 5 and the economizer 13.

An example in which pure water is used as a working fluid in the present embodiment will be described. The pure water as the working fluid in the intermediate loop is pressurized to 80 to 120 atm by the pressure increasing pump 49. The pure water pressurized by the pressurizing pump 49 is heated by the economizer 13 to become steam, passes through the header 50, and is heated to 460 to 5 by the heater 5.
It is heated to 90 ° C. and guided to the main steam heater 20. Main steam heater 20 heats the outlet steam of reactor 4 to 300 to 580 ° C.

The pure water flowing out of the main steam heater 20 is guided to the moisture separator / heater 21, and the steam at the outlet of the high pressure turbine is reduced to 250-350.
The purified water heated to ° C. and flowing out of the moisture separation heater 21 is then led to a high-pressure feed water heater 27. The pure water obtained by heating the reactor feed water to 190 to 240 ° C. by the high pressure feed water heater 27 then reaches the low pressure feed water heater 25.

The pure water whose condensed water is heated to 140 to 160 ° C. by the low-pressure feed water heater 25 returns to the boosting pump 49 and flows into the economizer 13. By using the combined power plant with the above configuration, the overall plant efficiency can be reduced by 5-15% for each power plant.
% Can be improved.

Next, a fourth embodiment according to the present invention will be described with reference to FIG. In FIG. 4, FIGS.
The same parts as those described above are denoted by the same reference numerals and the description of the overlapping parts will be omitted. This embodiment is different from the third embodiment in that a chemical injection pipe 51 is connected to the inflow pipe 31 of the intermediate loop as shown in FIG. 4, and an acidic chemical is stored in the chemical injection pipe 51. Tank 52 and tank storing alkaline chemical
53 are connected in parallel via infusion pumps 54 and 55 and stop valves 56 and 57, respectively.

In the present embodiment, the pH is controlled from 8.5 to 9.5 when pure water is used as the working fluid. This is an apparatus for improving the corrosion resistance of piping and equipment in the intermediate loop of the combined cycle power plant through which pure water flows.

The pH of the intermediate loop is measured by a working fluid meter (not shown). As a result, a predetermined value (p
H: 8.5 to 9.5), the alkaline chemical is injected from the tank 53 through the chemical injection pump 55 and the stop valve 57 from the chemical injection pipe 51 to the inlet pipe 31 of the intermediate loop.

On the other hand, when it is higher than the predetermined value, the acidic chemical is injected from the tank 52 through the chemical injection pump 54 and the stop valve 56 from the chemical injection pipe 51 to the inflow pipe 31 of the intermediate loop. In this way, the life of the intermediate loop piping and equipment can be extended.

Next, a fifth embodiment according to the present invention will be described with reference to FIG. FIG. 5 shows a main part of this embodiment, and other parts are omitted because they are the same as those in FIG. In the figure, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. The present embodiment is different from the embodiment of FIG. 1 in that a pressurizer 58 is provided in the outlet pipe 33 of the intermediate loop located at the outlet side of the exhaust heat recovery boiler 3 to supply pure water of the working fluid in the intermediate loop. That is, it can be operated as a single-phase flow of liquid.

That is, the pressurizer 58 is provided at the outlet of the exhaust heat recovery boiler 3 to pressurize the pure water in the intermediate loop so that a high-temperature liquid state can be maintained without boiling.
In this case, as described in the third embodiment shown in FIG. 3, the exhaust heat recovery boiler 3 has a configuration in which the heat transfer space 29 is built in without being divided into the economizer 13 and the heater 5, and thereby, the intermediate Handling such as control of the working fluid in the loop becomes easy.

Next, a sixth embodiment according to the present invention will be described with reference to FIG. FIG. 6 shows a main part of the present embodiment, and other parts are omitted because they are the same as those in FIG. In the figure, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the embodiment of FIG. 1 in that a dissolved salt injection pipe 59 is connected to the inflow side pipe 31 of the intermediate loop,
This is because a dissolved salt supply tank 61 is connected to the dissolved salt injection pipe 59 via a valve 60. The dissolved salt supply tank 61 is provided with a heater 62.

In this embodiment, a dissolved salt, a nitrite-based dissolved salt HTS and a liquid metal are used as the working fluid of the intermediate loop. The dissolved salt is obtained by melting a solid salt at a high temperature, and has a melting point of about 300 to 1000 ° C. Examples of using these working media will be described.

An example in which a dissolved salt is used as the working fluid of the intermediate loop will be described. Piping 59 at the inlet of the circulation pump 32,
It is connected to a dissolved salt supply tank 61 via a valve 60. A heater 62 is provided in the dissolved salt supply tank 60, and is used to heat the dissolved salt to a liquid state at the time of use. As the dissolved salt, a salt having a high boiling point, which does not boil at various points in the intermediate loop, and has excellent heat transfer characteristics is used. Further, since the dissolved salt is a salt, it has high chemical stability and is safe. For this reason, since the system of the intermediate loop can be maintained at a low pressure in a single phase, the design and manufacture of the piping system and the like become easy.

A case will be described where a nitrite-based dissolved salt HTS (NaNO ₃ -KNO ₃ -NaNO ₂ ) is used as the dissolved salt as the working fluid. Nitrous acid dissolved salt HTS is NaNO
₃ -KNO ₃ -NaNO _2, respectively 7-44-49mol
%, And exists as a liquid in the temperature range 150 to 590 ° C used as the working fluid of the intermediate loop. Therefore, it can be handled as a low-pressure single-phase flow in the intermediate loop. It has many uses in chemical engineering equipment, etc., and is stable and safe and has excellent properties as a heat transfer medium.
From this, since the system of the intermediate loop can be maintained at a low pressure with the liquid single phase of the dissolved salt, the design, manufacture and operation of the piping system and the like become easy.

An example in which liquid metal is used as the working fluid of the intermediate loop will be described. Na, P as liquid metal
At least one of b, K and NaK is used. Liquid metal exists as a liquid in the temperature range 150 to 590 ° C, which is used as the working fluid of the intermediate loop, like the dissolved salt.
Has excellent heat transfer characteristics. For this reason, since the system of the intermediate loop can be maintained at a low pressure in a single phase, the design, manufacture, and operation of the piping system and the like are facilitated.

Next, a seventh embodiment according to the present invention will be described with reference to FIG. FIG. 7 shows a main part of the present embodiment, and other parts are omitted because they are the same as those in FIG. In the figure, the same portions as those in FIGS. 1 and 6 are denoted by the same reference numerals, and the description of the overlapping portions will be omitted. This embodiment differs from the embodiment of FIG. 6 in that two valves are provided upstream of the inflow pipe 31 of the intermediate loop.
63 and 64 are connected in parallel, pipes 65 and 66 are connected to the valves 63 and 64, respectively, and an expansion tank 67 is connected to the pipes 65 and 66, which is suitable for using a dissolved salt or liquid metal as a working fluid. Device.

That is, when one of the pipes 66 is connected to the downstream side of the valve 63 of the intermediate loop via the valve 64 and the expansion tank 67 starts up the combined power generator from room temperature in a stopped state to high temperature in a steady state, The volume expansion of the working fluid in the intermediate loop can be absorbed. For this reason, it is possible to prevent the generation of extra stress in the system of the intermediate loop.

Next, an eighth embodiment according to the present invention will be described with reference to FIG. FIG. 8 shows a circuit configuration of the present embodiment. In the figure, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. The present embodiment differs from the embodiment of FIG. 1 in that an inlet stop valve 68 is provided in the inflow pipe 31 of the intermediate loop, and an outlet stop valve 69 is provided in the outflow pipe 33.
That is, the cycle is such that the nuclear power plant 1 or the gas turbine power plant 2 can operate independently.

According to the present embodiment, the low-pressure feed water heater 25 and the main steam heater on the side of the boiling water nuclear power plant 1
By providing stop valves 68 and 69 at the inlet and outlet of 20, the working fluid in the intermediate loop can be stopped, so that the nuclear power plant and the gas turbine power plant are thermally separated, and each can operate independently. It becomes possible. Thus, even when one of the power plants is stopped due to a periodic inspection or the like, the other power plant can be operated independently.

Next, a ninth embodiment according to the present invention will be described with reference to FIG. FIG. 9 is a circuit diagram for explaining the configuration of the present embodiment. The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the embodiment of FIG. 1 in that the heat transfer pipe 29 is provided in the exhaust heat recovery boiler 3.
In addition, the auxiliary steam heater 70 is incorporated to provide the auxiliary steam required for the nuclear power plant and the heat demand such as cooling and heating in the adjacent area.

That is, in this embodiment, the auxiliary steam heater is held in the exhaust heat recovery boiler 3 by the heat transfer tube 29.
A supplementary steam heater 70 is provided, one end of the supplementary steam heater 70 is connected to a makeup water pipe 71, and the other end is connected to a supplementary steam pipe 72, and the makeup water is heated to generate supplementary steam. Auxiliary steam is required for nuclear power plants, and is used for cooling and heating in the plant and for heating and cooling loads in the adjacent area.

Next, a tenth embodiment according to the present invention will be described with reference to FIG. FIG. 10 shows only the main part of the present embodiment, and other parts are omitted because they are the same as FIG. 1 or FIG. The present embodiment has a configuration in which electricity of a gas turbine generator is used as an emergency power source which is always required in a nuclear reactor system. That is, as shown in FIG. 10, the system system 76 is connected to the line 73 of the generator 17 directly connected to the gas turbine 15 via the circuit breaker 74, and the reactor service system 77 is connected to the circuit breaker 75 connected in parallel. ing.

In this embodiment, an example in which electricity of a gas turbine generator provided with a backup of a normal power supply of a nuclear reactor system is described.
The electric power generated by the generator 17 by the driving of the
Power is transmitted to the system 76 via the above. A part of this electric power is supplied via the circuit breaker 75 as backup electric power for the nuclear reactor ordinary system 75, for example, the nuclear reactor ordinary power system such as the reactor water purification system and the condensate makeup water system. As a result, there is an effect that the load on the conventionally used emergency power generator is greatly reduced.

Next, an eleventh embodiment according to the present invention will be described with reference to FIG. This embodiment is an example in which a gas turbine generator attached to an emergency power supply of a reactor system is used similarly to the tenth embodiment, and a gas in which three emergency power supplies requiring three systems are installed. The configuration is such that a turbine generator is used.

Emergency power sources such as a residual heat removal system of a nuclear reactor and a high-pressure core water injection system are provided with three independent power sources from the viewpoint of reliability for ensuring safety. In response to this, in the present embodiment, as shown in FIG. 11, three generators 17, 17a, 17b of the gas turbines 15, 15a, 15b in the gas turbine power plant 2 are provided, and the reactor emergency system A79, The configuration is such that power can be supplied to the reactor emergency system B79a and the reactor emergency system C79b.

That is, the electric power of the first gas turbine 15 and the gas turbine generator 17 is transmitted from the line 73 to the system 76 via the circuit breaker 74, and is also transmitted to the reactor system via the circuit breakers 75 and 78. 77, It is configured to be able to supply power to the reactor emergency system A79. The power of the second gas turbine 15a and the generator 17a can be supplied from the line 73a to the system 76a via the circuit breaker 74a, and can also be supplied to the reactor emergency system A79b via the circuit breaker 78a. I do.

The electric power of the third gas turbine 15b and the generator 17b is sent from the line 73b to the system 76b via the circuit breaker 74b, and is also supplied to the reactor emergency system C79b via the circuit breaker 78b. A configuration that can be used.

The conventional and emergency power supplies for a nuclear reactor having such a configuration do not require three independent emergency power generators as in the prior art, and can greatly simplify and reduce the cost. There is.

Next, a twelfth embodiment according to the present invention will be described with reference to FIG. FIG. 12 shows a circuit configuration of the present embodiment. In FIG. 12, the same parts as those in FIG. 1 or FIG. 1 and FIG. 3 is different from FIG. 1 or FIG. Nuclear power plant 1a, a low-boiling medium power plant 81 having a low-pressure turbine 8 as a component, a gas turbine power plant 2, and an intermediate loop (31, 32, 33,
36, 37, 38).

That is, the nuclear power plant 1a is different from FIG. 1 in that the low-pressure turbine 8 and the low-pressure feedwater heater 25 are omitted, and the generator 9 is directly connected to the high-pressure turbine 7. The low-boiling medium power plant 81 has a low-boiling medium cycle 82
The low-boiling medium cycle 82 includes an evaporator 80,
Gas-liquid separator 83, low pressure turbine 8, absorber 84, condenser 85,
It has a fluid pump 86, a regenerator 87 and a circuit having a circulation path.

The gas-liquid separator 83 and the regenerator 87 are connected by piping, and the regenerator 87 and the absorber 84 are also connected by piping. The heat transfer tube 88 in the evaporator 80 is connected to the steam outlet of the high-pressure turbine 7 and the inflow-side water supply pipe 11 of the water supply pump 12. The outlet steam of the high-pressure turbine 7 is introduced as a high-temperature heat source into the heat transfer tube 88 of the evaporator 80, and the working fluid from the regenerator 87 of the low-boiling medium cycle 82 is heated and evaporated. The reactor cooling water condensed in the evaporator 80 is pressurized by the feed water pump 12 and heated by the high pressure feed water heater 27,
Supplied to

The gas flowing out of the evaporator 80 flows into the gas-liquid separator 83, and the gas from which the drain has been separated is introduced into the low-pressure turbine 8. The gas working in the low-pressure turbine 8 is supplied to the absorber 84
Is condensed in a condenser 85, pressurized in a fluid pump 86, heated in a regenerator 87, and supplied to an evaporator 80. The efficiency of the plant can be further increased by setting the low-pressure turbine 8 to a low-boiling medium cycle.

The low-boiling medium cycle 82 is a carina cycle using a mixed fluid of water and ammonia as the working fluid, or a cycle using Florinol 85 as the working fluid. Thereby, it operates effectively and safely as a low boiling point medium, and contributes to the power generation efficiency of the plant.

Next, a thirteenth embodiment according to the present invention will be described. In this embodiment, the heat transfer tubes 26, 28, 29, 34, 35, and 88 in the first to twelfth embodiments are made of a plurality of metal elements so as to be in close contact between the inner tube and the outer tube. An object of the present invention is to form a double tube structure by providing a metal braided body obtained by alternately braiding a band formed by bundling wires in a net shape. The metal braid may be composed of a dissimilar metal, and may be plated on the surface.

With such a double tube structure,
The intermediate loop prevents radioactive substances contained in the working fluid (steam) from the nuclear power plants 1 and 1a from being mixed or leaked into the gas turbine power plant 2 and the atmosphere, and prevents leakage from the heat transfer tubes. Can be. In addition, when the inner tube and the outer tube leak, the leak can be easily detected, and the soundness of the heat transfer tube can be maintained.

[0084]

According to the present invention, a gas turbine power plant is provided in addition to a plant configuration of a nuclear power plant alone and connected as a cycle, so that the temperature difference from a high-temperature heat source becomes large, and thus the power generation efficiency is greatly increased. To improve. Further, the efficiency can be further improved because the low-boiling-point medium is provided in parallel. In the prior art, it was difficult to realize combined power generation with a boiling water nuclear power plant because the radioactive fluid was directly introduced into the steam turbine. Power generation facilities can be provided.

[Brief description of the drawings]

FIG. 1 is a circuit diagram showing a first embodiment of a combined cycle power plant according to the present invention.

FIG. 2 is a block diagram showing a second embodiment of the combined cycle power plant according to the present invention.

FIG. 3 is a circuit diagram showing a third embodiment of the combined cycle power generation equipment according to the present invention.

FIG. 4 is a circuit diagram showing a fourth embodiment of the combined cycle power plant according to the present invention.

FIG. 5 is a circuit diagram showing a main part of a fifth embodiment of the combined cycle power generation equipment according to the present invention.

FIG. 6 is a circuit diagram showing a main part of a sixth embodiment of the combined cycle power generation equipment according to the present invention.

FIG. 7 is a circuit diagram showing a main part of a seventh embodiment of the combined cycle power generation equipment according to the present invention.

FIG. 8 is a circuit diagram showing an eighth embodiment of a combined cycle power plant according to the present invention.

FIG. 9 is a system diagram showing a ninth embodiment of a combined cycle power plant according to the present invention.

FIG. 10 is a system diagram showing a main part of a tenth embodiment of the combined cycle power plant according to the present invention.

FIG. 11 is a circuit diagram showing a main part of an eleventh embodiment of a combined cycle power plant according to the present invention.

FIG. 12 is a circuit diagram showing a twelfth embodiment of a combined cycle power plant according to the present invention.

FIG. 13 is a system diagram showing a conventional combined cycle power plant.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Nuclear power plant, 2 ... Gas turbine power plant, 3 ... Waste heat recovery boiler, 4 ... Reactor, 5 ... Main steam heater, 6 ... Main steam pipe, 7 ... High pressure turbine, 8 ... Low pressure turbine, 9 ... Generator, 10… Condenser, 11… Water supply pipe, 12… Water supply pump, 13… Energy saving machine, 14… Combustion chamber, 15… Gas turbine, 16
... compressor, 17 ... generator, 18 ... waste gas pipe, 19 ... exhaust pipe, 20
… Main steam heater, 21… Moisture separation heater, 22… Steam piping,
23 ... condensing system piping, 24 ... condensing pump, 25 ... low pressure feed water heater, 26 ... heat transfer tube, 27 ... high pressure feed water heater, 28 ... heat transfer tube, 29
... heat transfer tube, 30 ... exhaust pipe, 31 ... inflow side pipe, 32 ... circulation pump, 33 ... outflow side pipe, 34 ... heat transfer pipe, 35 ... heat transfer pipe, 36, 3
7, 38: Flow pipe, 39: Reactor control device, 40: Gas turbine control device, 41: Steam turbine, 42: Reactor outlet steam pressure, 43: Pressure detector, 44: Steam control valve, 45 ... Feedback Control, 46: Steam temperature at steam turbine inlet, 47: Temperature detector, 48: Gas turbine fuel control valve, 49 ... Boost pump, 50 ... Steam reservoir, 51 ... Chemical liquid injection pipe, 52 ... Acid chemical liquid storage tank, 53 ... Alkaline chemical storage tank, 54, 55 injection pump, 56, 57 stop valve, 58 pressurizer, 59 dissolved salt injection piping, 60 valve, 61 dissolved salt supply tank, 62 heater, 63, 64 ... Valve, 65, 66… Piping, 67… Expansion tank, 68…
Inlet stop valve, 69 ... Outlet side stop valve, 70 ... Auxiliary steam heater, 71 ... Make-up water pipe, 72 ... Auxiliary steam pipe, 73 ... Track, 74, 75
... Circuit breaker, 76 ... System system, 77 ... Reactor service system, 78 ... Circuit breaker, 79 ... Reactor emergency system, 80 ... Evaporator, 81 ... Low boiling medium power generation plant, 82 ... Low boiling medium cycle, 83 ... Gas-liquid separator, 84: absorber, 85: condenser, 86: fluid pump, 87: regenerator, 88: heat transfer tube.

Claims (13)

[Claims] 1. A nuclear power plant for generating electricity by driving a steam turbine and rotating a generator using steam generated in a boiling water reactor as working steam, a gas turbine power plant attached to the nuclear power plant, A waste heat recovery boiler connected to a gas turbine of a gas turbine power plant, and a feed water heater and a main steam heater installed in the nuclear power plant at both ends of a heat transfer tube incorporated in the waste heat recovery boiler. And an intermediate loop connected to form a circulation path. 2. The reactor according to claim 1, wherein the reactor includes a reactor controller for controlling a reactor outlet steam pressure, and the steam turbine includes a steam pressure detector for detecting a steam pressure state quantity from the reactor controller. A steam turbine control device having a steam control valve for inputting a signal, wherein the gas turbine includes a steam temperature detector for inputting a turbine inlet steam temperature signal from the steam turbine control device, and a fuel control valve. The combined power generation facility according to claim 1, further comprising a device. 3. The combined cycle power plant according to claim 1, wherein the working fluid of the intermediate loop is made of pure water or cooling water whose pH is adjusted to 8.5 to 9.5. 4. A molten salt supply tank is provided on the intermediate loop at an inlet side of the waste heat recovery boiler, and a working fluid flowing through the intermediate loop is composed of a dissolved salt, a nitrite-based dissolved salt, or a liquid metal. The combined power generation facility according to claim 1. 5. The combined cycle power plant according to claim 1, wherein a pressurizer is provided in the intermediate loop. 6. The combined cycle power plant according to claim 1, wherein an expansion tank for absorbing a volume expansion of the working fluid is provided in the intermediate loop. 7. The composite according to claim 1, wherein a stop valve is provided in each of an inflow side pipe and an outflow side pipe connected to the heat transfer pipe incorporated in the exhaust heat recovery boiler of the intermediate loop. Power generation equipment. 8. A first and a second circuit breaker are connected in parallel to the gas turbine generator, a system is connected in series to the first circuit breaker, and a reactor service system is connected to the second circuit breaker. The combined power generation facility according to claim 1, wherein the combined power generation facility is connected in series. 9. The gas turbine generator according to claim 1, further comprising:
Three power generators are arranged in parallel, and a system system, a reactor service system, and a first reactor emergency system are connected in parallel to the first gas turbine generator via circuit breakers, respectively,
The system and the second emergency system are connected in parallel to each other via a circuit breaker, respectively, and the system and the third emergency system are respectively connected to the third gas turbine generator via a circuit breaker. 2. The method according to claim 1, wherein the connection is made in parallel.
The combined power plant described. 10. An auxiliary steam heater for injecting make-up water into the exhaust heat recovery boiler is installed, and downstream of the auxiliary steam heater, the auxiliary steam for the nuclear power plant and piping for cooling and heating equipment in an adjacent area. The combined power generation facility according to claim 1, wherein 11. A reactor using light water as a coolant, a main steam heater connected to the reactor via a main steam pipe, and a high-pressure turbine connected to the main steam heater via a main steam pipe. A generator connected to the high-pressure turbine, an evaporator provided with a heat transfer tube through which steam flowing out of the high-pressure turbine flows, and a feed water heating connected to a heat transfer tube outlet side of the evaporator via a pure water pump. , A feed pipe connecting the feed water heater and the reactor, a gas-liquid separator into which the low-boiling-point medium vapor heated by the heat transfer pipe in the evaporator is separated, and separated by the gas-liquid separator. A low-pressure turbine rotated by the low-boiling-point medium steam, a generator connected to the low-pressure turbine,
An absorber into which the low-boiling-point medium vapor flowing out of the low-pressure turbine flows, a condenser connected to the absorber, a regenerator connected to the condenser via a fluid pump, the regenerator and the evaporator, A return pipe for connecting the heat transfer pipe of the feed water heater, and an intermediate loop pipe for discharging steam that has heated the heat transfer pipe.
A economizer in the exhaust heat recovery boiler connected to the intermediate loop pipe via a booster pump, a superheater in the exhaust heat recovery boiler connected to the economizer, the superheater and the main steam heater, And an intermediate loop pipe connecting the main steam heater and the feed water heater. 12. The combined cycle power plant according to claim 11, wherein the low-boiling medium comprises a mixture of water and ammonia or Florinol 85. 13. A heat transfer tube incorporated in a main steam heater, a moisture separation heater, a feed water heater, or an evaporator for exchanging heat with a working fluid flowing through the intermediate loop pipe, wherein a heat transfer tube is disposed between the inner tube and the outer tube. 13. The combined power generation facility according to claim 1, wherein the combined power generation facility has a double-pipe structure in which a metal braid is inserted into the power generator.