JP2001004791A - Reactor heat utilization system - Google Patents

Abstract

PROBLEM TO BE SOLVED: To raise the safety of a reactor heat utilization system and heat utilization efficiency. SOLUTION: A reactor 11 for heating cooling water and sending it out, a turbine 12 rotated by cooling water, a compressor 21 driven by the turbine 12 for compressing loop circulation water, a heat utilization side heat exchanger 22 for exchanging heat between utility water for finally utilizing the reactor 11 heat and loop circulation water and a reactor side heat exchanger 14 whereto cooling water from the turbine 12 and loop circulation water from the compressor 12 or the heat utilization side heat exchanger 22 are supplied and heat in them is exchanged when the utility water is heated by the heat of the reactor 11 and the heat of cooling water and loop circulation water is discharged when the utility water cooled by the heat of the reactor 11 are provided to raise the safety of the reactor heat utilization system and heat utilization efficiency and to lower the cost.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear heat utilization system capable of safely and efficiently using electric power and heat from a nuclear power plant.

[0002]

2. Description of the Related Art Today, a heat utilization system (so-called cogeneration system) has been proposed for the purpose of recovering steam from a nuclear power plant and heat of cooling water for an engine or the like to efficiently use energy.

[0003] FIG. 12 is a schematic configuration diagram of a nuclear heat utilization system that performs desalination of seawater and the like using electric power and heat from a nuclear power plant.

In the drawings in this specification, pipes through which gas such as steam flows are shown by dotted lines, and pipes through which liquid flows are shown by solid lines.

[0005] The seawater desalination system shown in FIG. 12 is a distillation type seawater desalination system, and is a boiling water reactor (BWR).
The high-pressure steam from 100 is supplied to the high-pressure turbine 101, and after the work in the high-pressure turbine 101, is supplied to the low-pressure turbine 102 and the heat exchanger 103 of the seawater desalination apparatus. The high-pressure turbine 101
Further, a generator 104 is connected to the low-pressure turbine 102.

Then, the steam exchanges heat with seawater in the heat exchanger 103, and the low-pressure turbine 1
02 together with the steam from the water 02 to return to seawater by condensing water, sent to a feedwater heater 107 by a feedwater pump 106, and heated there to be heated by a boiling water reactor 100 (hereinafter, except in special cases). , Simply referred to as the reactor).

[0007] At this time, the seawater with which the steam exchanges heat in the heat exchanger 103 is seawater for desalination, and the seawater is evaporated and desalinated by heat from the steam, and the concentrated seawater is drained.

By the way, in the case of such a configuration, the heat exchanger 1
When a defect such as a hole is created in the reactor 03, if the steam supplied from the reactor 100 is contaminated with radioactivity,
The contaminated steam mixes with the seawater to be desalinated, and the desalinated water may be contaminated by radioactivity.

Therefore, as shown in FIG.
It is conceivable to provide an intermediate heat exchanger 108 so that steam from zero does not directly exchange heat with seawater via the heat exchanger 103.

In this case, since the steam from the reactor 100 exchanges heat only through the intermediate heat exchanger 108, even if a hole is made in the intermediate heat exchanger 108, the desalinated water is contaminated. Fear is greatly reduced.

Of course, in principle, both the secondary side and the secondary side of the intermediate heat exchanger 108 may be damaged, and in order to cope with such a case, the safety is increased by using a large number of the intermediate heat exchangers 108. Is increasing.

[0012]

However, in the nuclear heat utilization system having the above configuration, since the heat of the steam from the reactor 100 is recovered through the heat exchanger 103, it is difficult to enhance the heat utilization efficiency. In addition to the problem, there is a problem that providing a plurality of intermediate heat exchangers 108 increases the cost.

In a desert area, a nuclear heat utilization system is sometimes used for the purpose of desalination of seawater rather than power generation. However, in a nuclear heat utilization system for the purpose of power generation, nuclear heat utilization system for the desalination of seawater is used. In view of the necessity of handling steam at a higher pressure than the system, the pressure resistance of the members must be increased, and there is a problem that the system is excessively equipped for the intended use.

Accordingly, an object of the present invention is to provide a low-cost nuclear heat utilization system that enhances the safety of the nuclear heat utilization system and enhances the heat utilization efficiency.

[0015]

Means for Solving the Problems To solve the above problems, the invention according to claim 1 comprises a reactor for heating and sending a first refrigerant, a turbine rotated by the first refrigerant, and a turbine. A compressor that compresses the second refrigerant driven by the heat-utilization-side heat exchanger that performs heat exchange between the second refrigerant and the heat-utilization-side refrigerant that finally uses the heat of the nuclear reactor;
When the first refrigerant from the turbine and the second refrigerant from the compressor or the heat utilization side heat exchanger are supplied and the heat utilization side refrigerant is heated by the heat of the nuclear reactor, these first refrigerants are used. When exchanging heat between the first refrigerant and the second refrigerant and cooling the heat utilization-side refrigerant by the heat of the nuclear reactor, the heat generated by the first refrigerant and the second refrigerant dissipates the heat of the first refrigerant and the second refrigerant. Having an exchanger and
It is characterized by improving the safety of the nuclear heat utilization system, increasing the heat utilization efficiency, and reducing the cost.

[0016] The invention according to claim 2 is characterized in that the reactor is any one of a boiling water reactor, a pressurized water reactor, a liquid metal cooled reactor and a gas cooled reactor.

The invention according to claim 3 is characterized in that the refrigerant on the heat utilization side is seawater supplied to a vapor compression type seawater desalination system.

The invention according to claim 4 is characterized in that the heat utilization side refrigerant is seawater supplied to a reverse osmosis type seawater desalination system.

According to a fifth aspect of the present invention, the reactor-side heat exchanger comprises a tank, a plurality of first heat transfer tubes through which the first refrigerant flows, and a second refrigerant which passes through the tank. A plurality of second heat transfer tubes that flow through the first heat transfer tube stored in the tank and a third refrigerant that makes thermal contact between the first refrigerant that flows through the first heat transfer tube and the second refrigerant that flows through the second heat transfer tube. It is characterized by enhanced safety.

According to a sixth aspect of the present invention, the third refrigerant has a melting point lower than the lowest temperature of the first refrigerant and the second refrigerant at atmospheric pressure, and the first refrigerant and the second refrigerant at atmospheric pressure. Characterized by having a boiling point higher than the maximum temperature of

According to a seventh aspect of the present invention, the heat exchanger on the reactor side has a tank partitioned into two chambers, and a plurality of heat pipes provided in communication with the respective rooms. The heat of the first or second refrigerant flowing into the room is transmitted to the other room via the heat pipe, and is transmitted to the second or first refrigerant flowing into the room, thereby enhancing safety. It is characterized by.

In the invention according to claim 8, when returning the first refrigerant from the heat exchanger on the reactor side to the nuclear reactor, the first refrigerant extracted from a part of the first refrigerant from the nuclear reactor or the turbine. An injector is provided to increase the pressure and temperature of the first refrigerant that is injected into the reactor and returns to the reactor, thereby increasing the thermal efficiency of the system and reducing the cost.

The invention according to claim 9 is characterized in that a generator is driven by a part of the first refrigerant from the nuclear reactor to generate electric power.

[0024]

DESCRIPTION OF THE PREFERRED EMBODIMENTS Embodiments of the present invention will be described with reference to the drawings. FIG. 1 is a schematic configuration diagram of a nuclear heat utilization system applied to the description of the first embodiment.

The nuclear heat utilization system includes a boiling water reactor (BWR) 11 for supplying high-temperature steam, the reactor 11
12 supplied with high-temperature steam from the turbine, rotates, the reactor-side heat exchanger 13, the feedwater pump 14, the main steam (the reactor 1)
Feed water heater 15 using steam supplied directly from 1),
It has a compressor 21 connected to the rotating shaft of the turbine 12, a heat utilization side heat exchanger 22 to which steam from the compressor is supplied, and the like.

In the following description, the refrigerant (first refrigerant) circulating through the reactor 11, the turbine 12, the reactor-side heat exchanger 13, the feed water pump 14, and the feed water heater 15 will be referred to as cooling water.
The refrigerant (second refrigerant) circulating through the compressor 21, the heat utilization-side heat exchanger 22, and the reactor-side heat exchanger 13 is passed through loop circulating water,
The refrigerant that exchanges heat with the loop circulating water in the heat utilization-side heat exchanger 22 (the refrigerant on the heat utilization side) will be described as utilization water.

With such a configuration, the steam from the reactor 11 is supplied to the turbine 12 to rotate the turbine 12 and is condensed in the reactor-side heat exchanger 13. Thereafter, the water is pumped by a feed water pump 14, heated by a feed water heater 15, and circulated to the nuclear reactor 11.

A part of the high temperature steam from the reactor 11 is supplied to the feed water heater 15, and the cooling water from the feed pump 14 is combined with the high temperature steam to form the reactor 11
, The temperature of the cooling water is raised.

Therefore, the temperature of the steam supplied from the nuclear reactor 11 can be increased accordingly, or the amount of steam can be increased.

On the other hand, a compressor 21 is connected to the turbine 12, and loop circulating water is circulating through the compressor 21. The loop circulating water is heated by steam of the cooling water from the turbine 12 when passing through the reactor-side heat exchanger 13, and is supplied to the compressor 21 as steam.

Therefore, the compressor 21 compresses the vaporized loop circulating water without causing liquid compression. Since this compression process can be regarded as substantially adiabatic compression, the temperature and pressure of the loop circulating water increase and are supplied to the heat utilization side heat exchanger 22.

Since the use water is circulated in the heat use side heat exchanger 22, the use water is heated by the loop circulating water to become hot water, so that the heat of the reactor can be used safely. Become.

At this time, the loop circulating water is compressed by the compressor 21 to have a high temperature and a high pressure, and a heat pump cycle is formed.
In this case, more heat can be recovered and used as compared with the case where the heat is simply exchanged with the steam and the case where the heat is directly exchanged with the steam from the nuclear reactor 11.

In the above description, the case where the heat utilization apparatus is a heat pump cycle in which the heat from the reactor 11 is recovered and used is described. As shown in FIG. 2, the loop circulating water is circulated in the reverse direction. This makes it possible to form a refrigeration cycle for cooling the water used.

However, in this case, the reactor-side heat exchanger 1
In 6, the heat is not exchanged between the loop circulating water and the steam from the turbine 12, but the seawater is exchanged with the loop circulating water and the cooling water.

When the high-temperature utilization water circulates through the heat utilization-side heat exchanger 22, the utilization water heats the loop circulation water to evaporate the loop circulation water. As a result, steam is supplied to the compressor 21, and the steam is compressed into high-temperature and high-pressure steam.

Thereafter, the vapor of the loop circulating water releases heat to seawater in the reactor-side heat exchanger 16 to be condensed, and circulates to the heat utilization-side heat exchanger 22. The used water loses heat by the amount of heating the loop circulating water and is cooled.

As described above, since the steam of the cooling water from the reactor 11 does not directly exchange heat with the water to be used, even if the reactor-side heat exchangers 13 and 16 are damaged, the cooling water is utilized. The risk of water contamination is reduced.

Of course, the steam from the turbine 12 directly exchanges heat with the loop circulating water in the reactor-side heat exchangers 13 and 16, so if the reactor-side heat exchangers 13 and 16 are damaged, The loop circulating water may become contaminated.

However, in the case of FIG. 1, since the loop circulating water is condensed in the heat utilization side heat exchanger 22, the pressure of the loop circulating water supplied to the reactor side heat exchanger 13 is discharged from the compressor 21. Although the pressure is lower than the pressure at the time of the cooling, the pressure is still higher than the atmospheric pressure, and the pressure of the steam from the turbine 12 can be regarded as substantially the atmospheric pressure. Therefore, the possibility that the cooling water is mixed with the loop circulation water is reduced. I have.

In the case of FIG. 2, since the loop circulating water compressed from the compressor 21 is supplied to the reactor-side heat exchanger 16 as it is, the pressure is higher than the pressure of the steam from the turbine 12.

Therefore, even when the reactor-side heat exchangers 13 and 16 are damaged, the occurrence of a situation in which contaminated cooling water is mixed with the loop circulating water is extremely small.

In the above description, the case where the steam supplied to the turbine 12 is the cooling water of the nuclear reactor 11 has been described. However, it is clear that the cooling water does not need to be used directly. Steam may be separately generated by heat, and the steam may be supplied to the turbine 12.

It goes without saying that not only the main steam but also the steam extracted from the turbine 12 may be used as the heat source of the feed water heater 15.

Furthermore, although a boiling water reactor has been described as an example of the reactor 11, the present invention is not limited to this, and a pressurized water reactor (PWR), a liquid metal cooled reactor (LMR), It may be a gas-cooled nuclear reactor (GCR) or the like.

Next, a second embodiment of the present invention will be described. In addition, about the same structure as the said embodiment, the same code | symbol is turned down and description is abbreviate | omitted suitably.

As described above, the present invention is not limited to the boiling water reactor 11 as the nuclear reactor. Therefore,
In the present embodiment, a nuclear heat utilization system using a gas-cooled nuclear reactor (GCR) as another nuclear reactor will be described.

The nuclear heat utilization system in this case includes a gas-cooled nuclear reactor 31 as shown in FIG.
The turbine 32 is supplied with high-temperature gas from the turbine and rotates, the reactor 32 heat exchanger 33 that radiates heat of the gas discharged from the turbine 32 to generate a low-temperature gas, and the turbine 32 drives to lower the temperature. Gas compressor 3 for compressing gas
4. It has a compressor 21 driven by the turbine 32 to compress the vaporized loop circulating water, a heat utilization side heat exchanger 22 for exchanging heat between the loop circulating water and utilization water, and the like.

The high-temperature gas from the gas-cooled nuclear reactor 31 is supplied to the turbine 32 to rotate the turbine 32, and thereafter is supplied to the reactor-side heat exchanger 33.

Here, the gas is cooled by heating the loop circulating water to lower the temperature, and is compressed by the gas compressor 34 to become a high-temperature gas and returns to the gas-cooled nuclear reactor 31.
On the other hand, the loop circulating water is heated by the gas to become steam and supplied to the compressor 21.

The compressor 21 is driven by a turbine 32, whereby high-temperature and high-pressure steam is supplied to the heat-use-side heat exchanger 22.

Accordingly, the water used in the heat-use-side heat exchanger 22 exchanges heat with the loop circulating water whose temperature has been increased by the compressor 21 to increase the temperature.

As shown in FIG. 2, it is also possible to circulate cooling water such as seawater through the reactor-side heat exchanger 33 and circulate loop circulating water in the reverse direction to cool the water used. is there.

As a result, the same operation principle as described above is established, and the same effect can be obtained.

Next, a third embodiment will be described. Note that the same components as those in the above-described embodiment are denoted by the same reference numerals, and description thereof will be omitted as appropriate.

In the embodiments described above, the case where the heat pump cycle and the refrigeration cycle are formed has been described. However, the present invention is not limited to this, and can be applied to a seawater desalination apparatus and the like. Thus, in the present embodiment, a case where such a seawater desalination apparatus is used will be described with reference to FIG. At this time, a case where the boiling water reactor 11 is used as the reactor described in the first embodiment will be described as an example.

In the nuclear heat utilization system in this case, the compressor 21 is driven by the turbine 12 and the compressor 2
1, freshwater vapor from which seawater evaporates is circulated.

The seawater to be desalinated is supplied to a steam condenser 37 via a reactor-side heat exchanger 35 and a seawater pre-heater 36.

At this time, the seawater is heated by the steam from the turbine 12 in the reactor-side heat exchanger 35, further heated in the seawater pre-heater 36, and brought to a substantially boiling point in a stage where it is supplied to the steam condenser 37. Has reached.

Accordingly, the steam condenser 37 is filled with steam, and the compressor 21 compresses the steam to raise the temperature and return the steam to the steam condenser 37. I have.

The steam from the compressor 21 heats seawater in the steam condenser 37 to promote evaporation and is condensed to be taken out as fresh water. The steam remaining in the steam condenser 37 has a high concentration. The depleted seawater is drained.

Since seawater supplied through the reactor-side heat exchanger 35 is pumped by a pump (not shown) or the like, even if the reactor-side heat exchanger 35 is damaged, the pressure relationship is not affected. There is very little risk of cooling water mixing with seawater.

Since the seawater of the steam condenser 37 is heated by the steam whose temperature has been increased by being compressed by the compressor 21, desalination can be performed efficiently.

There are various methods for desalinating seawater other than the above-mentioned distillation method. For example, a reverse osmosis device can be used.

FIG. 5 is a diagram showing a configuration of a nuclear heat utilization system using such a reverse osmosis device. In this case, a pump 39 is provided in the turbine 12, and seawater is supplied to the reverse osmosis device 38 by the pump 39. Pumping.

The reverse osmosis device 38 may have a known structure as shown in FIG.
Center pipe 40, mesh spacer 41, reverse osmosis membrane 4
2. The high-pressure seawater (supply water) is separated into fresh water (fresh water) and drainage water (concentrated water) by the reverse osmosis membrane 42 having the channel material 43 and the like. The reverse osmosis device 38 includes a plurality of elements having such a configuration.

It is known that the higher the temperature of the seawater sent to the reverse osmosis device 38 is, the more efficient the seawater is. Therefore, the seawater is heated by the reactor-side heat exchanger 13 and is driven by the turbine 12. Pump 39 with reverse osmosis device 3
To 8

As described above, since the steam from the turbine 12 and the seawater are heat-exchanged by the heat exchanger 13 on the reactor side, the steam is condensed in order to condense the steam from the turbine 12 as in the prior art. Seawater that has been cooled and the temperature of which has increased can be used without draining, thereby increasing thermal efficiency.

The appropriate pressure of seawater supplied to the reverse osmosis device 38 is 65 to 70 atm.
Since the pumping head is about 70 atm, a pump similar to the water supply pump 14 can be used as the seawater pumping pump 39 without using a special pump, so that versatility is improved and cost can be reduced. .

Next, a fourth embodiment of the present invention will be described with reference to FIG. Note that the same components as those in the above-described embodiment are denoted by the same reference numerals, and description thereof will be omitted as appropriate.

In each of the embodiments described so far, the cooling water condensed in the heat exchanger on the reactor side is circulated to the reactor 11 via the feed water pump 14 and the feed water heater 15.

In this embodiment, the main steam and the extracted steam from the turbine 12 are used as the driving steam in this embodiment.
An injector 44 for increasing the pressure of the cooling water is used.

The injector 44 is a pump having no movable part for driving water supply by a supersonic jet of steam to obtain a discharge pressure higher than the supply steam pressure, and the steam and the condensed cooling water come into direct contact with each other. Can also be considered a heat exchanger,
It has both functions of the feedwater heater 15 and the feedwater pump 14.

The injector 44 has the following configuration.
Simplified water supply system using multistage injectors by Shuichi Omori et al. (The Japan Society of Mechanical Engineers, The forefront of power and energy technology '
98, pp 183-185).

As described above, the feed water heater 15 and the feed pump 1
By using the injector 44 having both functions of the injector 4, the cost can be reduced by reducing the number of parts, and since the injector 44 has no movable parts, the reliability of operation is improved and the maintenance is facilitated.

Next, a fifth embodiment of the present invention will be described with reference to FIG. Note that the same components as those in the above-described embodiment are denoted by the same reference numerals, and description thereof will be omitted as appropriate.

In each of the embodiments described above, the case where power generation is not performed has been described. However, the present invention is not limited to this, and power generation may be performed.

The configuration shown in FIG. 8 supplies steam from the nuclear reactor 11 to the turbine 12 for driving the pump 39, the turbine 46 for driving the generator 45, and the feed water heater 15.

The turbine 4 for driving the generator 45
The steam from 6 is supplied to the reactor-side heat exchanger 13 together with the steam from the turbine 12 that drives the pump 39.

As a result, the energy generated in the nuclear reactor 11 can be used as electricity, and the heat can be efficiently recovered and used, thereby improving the convenience.

The structure for performing power generation and heat recovery is not limited to such a structure. For example, if attention is paid to the fact that the inlet pressure of the turbine 12 necessary for the pump 39 and the like used in the present invention can be operated even if it is lower than the pressure at the time of generating power in the boiling water reactor, it is possible to use nuclear power. The turbine for driving the pump 39 may be driven using steam from the turbine for power generation or extracted steam at the power plant.

FIG. 9 shows such a configuration. The high pressure turbine 47 is rotated by the steam from the nuclear reactor 11, and the exhaust steam is supplied to the low pressure turbine 48 and the turbine 12.

The low pressure turbine 48 and the turbine 1
The steam from 2 exchanges heat with seawater by the reactor-side heat exchanger 49 and returns to the reactor 11 via the feedwater pump 14 and the like.

Therefore, the heat can be efficiently used together with the supply of the electric power, and the economy and convenience are improved.

Next, a sixth embodiment of the present invention will be described with reference to the drawings. Note that the same components as those in the above-described embodiment are denoted by the same reference numerals, and description thereof will be omitted as appropriate.

The safety of the above-described heat exchanger on the reactor side and the heat exchanger on the heat utilization side is ensured from the pressure relation as described above. However, if safety is expected, FIGS. It is preferable to adopt a configuration as shown in FIG.

The heat exchanger 50 shown in FIG.
1. The tank 51 is formed by a plurality of primary heat transfer tubes 52 and secondary heat transfer tubes 53 provided through the inside of the tank 51, and the tank 51 is filled with a heat transfer medium 54.

Accordingly, even if a hole is formed in the primary heat transfer tube 52, the refrigerant (for example, cooling water) flowing through the primary heat transfer tube 52 only mixes with the heat transfer medium 54. It does not mix with the refrigerant flowing in the secondary heat transfer tube 53 (for example, loop circulating water), and even less with the water used. Therefore, the safety of the nuclear heat utilization system is enhanced.

At this time, as the heat transfer medium 54, the melting point at atmospheric pressure is lower than the minimum temperature of the cooling water and the loop circulating water, and the boiling point is higher than the maximum temperature of the cooling water and the loop circulating water. preferable.

As such a heat transfer medium 54, for example, 1
When the steam flowing through the secondary heat transfer tube 52 is 0.05 atm and the loop circulating water flowing through the secondary heat transfer tube 53 is 30 ° C., ethylene glycol or the like, which is known as an antifreeze, can be used.

When such a heat transfer medium 54 is used, since the heat transfer medium 54 does not solidify or boil, it is possible to prevent an increase in the internal pressure of the tank 51 and a change in the amount of heat transfer due to such a phase change. The safety of the heat utilization system increases.

The reactor-side heat exchanger 55 shown in FIG.
Is that the tank 56 is divided into the primary spaces 57 and 2 by the partition plate 59.
A baffle plate 60, 61 is provided in each of the spaces 57, 58, and these spaces 5
A plurality of heat pipes 62 communicate with 7, 58.

A heat transfer medium (not shown) is sealed in the heat pipe 62, and the heat transfer medium is heated by a refrigerant (for example, cooling water) flowing into the primary space 57, evaporates, and is heated to the secondary side. The refrigerant (for example, loop circulating water) that has risen into the space 58 and has flowed into the secondary space 58 is heated to lose heat and condensed, and the heat pipe 62 of the primary space 57 is heated.
It is designed to be stored at the bottom.

Therefore, even if a hole is formed in the heat pipe 62 in the primary space 57, the refrigerant flowing in the secondary space 58 is not mixed with the refrigerant flowing in the primary space 57, so that safety is improved. Increase.

[0095]

As described above, according to the nuclear heat utilization system of the present invention, the compressor is driven by the first refrigerant from the nuclear reactor to compress the second refrigerant, and the second refrigerant is compressed.
The heat exchange between the refrigerant and the heat utilization side refrigerant is performed, so that the heat utilization efficiency is improved.

Further, since the possibility that the coolant on the primary side and the coolant on the secondary side come into contact with each other on the reactor side heat exchanger is reduced, the safety can be further improved at low cost and easily.

[0097] Further, since the energy which has been conventionally thrown away into seawater or the like is used, the heat utilization rate is improved and the economic efficiency is improved.

[Brief description of the drawings]

FIG. 1 is a configuration diagram of a nuclear heat utilization system of a heat pump cycle applied to the description of a first embodiment of the present invention.

FIG. 2 is a configuration diagram when the nuclear heat utilization system in FIG. 1 is used as a refrigeration cycle.

FIG. 3 is a configuration diagram of a nuclear heat utilization system applied to the description of a second embodiment of the present invention.

FIG. 4 is a configuration diagram of a nuclear heat utilization system applied to the description of a third embodiment of the present invention.

FIG. 5 is a configuration diagram of a nuclear heat utilization system replacing FIG. 4;

FIG. 6 is a diagram showing a configuration of a reverse osmosis device.

FIG. 7 is a configuration diagram of a nuclear heat utilization system applied to the description of a fourth embodiment of the present invention.

FIG. 8 is a configuration diagram of a nuclear heat utilization system applied to the description of a fifth embodiment of the present invention.

9 is a configuration diagram of a nuclear heat utilization system replacing FIG.

FIG. 10 is a configuration diagram of a heat exchanger applied to the description of a sixth embodiment of the present invention.

FIG. 11 is a configuration diagram of a heat exchanger instead of FIG. 8;

FIG. 12 is a configuration diagram of a nuclear heat utilization system applied to a description of a conventional technique.

FIG. 13 is a configuration diagram of a nuclear heat utilization system applied to the description of a conventional technique.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 11 Nuclear reactor 12, 32 Turbine 13, 16, 33, 35, 49, 55 Reactor side heat exchanger 14 Feedwater pump 15 Feedwater heater 21 Compressor 22 Heat use side heat exchanger 34 Gas compressor 36 Seawater pre-heater 37 Steam condenser 38 Reverse osmosis device 39 Pump 43 Channel material 44 Injector 45 Generator 46 Turbine 47 High pressure turbine 48 Low pressure turbine 50 Heat exchanger 51, 56 Tank 52 Primary heat transfer tube 53 Secondary heat transfer tube 54 Heat medium 57 Primary space 58 Secondary space 59 Partition plate 60, 61 Baffle plate 62 Heat pipe

Claims (9)

[Claims] A reactor that heats and sends a first refrigerant; a turbine that is rotated by the first refrigerant; a compressor that is driven by the turbine to compress a second refrigerant; A heat-using-side heat exchanger that performs heat exchange between the heat-using-side refrigerant that finally uses heat and the second refrigerant; and a first refrigerant from the turbine and the compressor or the heat-using-side heat exchange. When the second refrigerant is supplied from the vessel and the heat on the heat utilization side is heated by the heat of the nuclear reactor, the first refrigerant and the second refrigerant are heat-exchanged, and the When cooling the refrigerant on the heat utilization side by the heat of the reactor, it has a nuclear reactor-side heat exchanger for releasing heat of the first refrigerant and the second refrigerant. system. 2. The nuclear reactor according to claim 1, wherein the nuclear reactor is one of a boiling water reactor, a pressurized water reactor, a liquid metal cooled reactor and a gas cooled reactor. Usage system. 3. The nuclear heat utilization system according to claim 1, wherein the refrigerant on the heat utilization side is seawater supplied to a seawater desalination system of a vapor compression system. 4. The nuclear heat utilization system according to claim 1, wherein the heat utilization side refrigerant is seawater supplied to a reverse osmosis type seawater desalination system. 5. The reactor-side heat exchanger includes a tank, a plurality of first heat transfer tubes through which the first refrigerant flows, and the second refrigerant flows through the tank. A plurality of second heat transfer tubes, and the first heat transfer tubes stored in the tank.
The first refrigerant flowing through the heat transfer tube and the second refrigerant flowing through the second heat transfer tube
The nuclear heat utilization system according to any one of claims 1 to 4, further comprising a third refrigerant that makes thermal contact with the refrigerant. 6. The third refrigerant has a melting point lower than the minimum temperature of the first refrigerant and the second refrigerant at atmospheric pressure, and forms the first refrigerant and the second refrigerant at atmospheric pressure. The nuclear heat utilization system according to claim 5, having a boiling point higher than the maximum temperature. 7. The reactor-side heat exchanger has a tank partitioned into two chambers, and a plurality of heat pipes provided in communication with each of the chambers, and the first heat exchanger flowing into one of the chambers. The heat of the 1st or 2nd refrigerant | coolant is transmitted to the other room via the said heat pipe, and is transmitted to the 2nd or 1st refrigerant | coolant which flowed into the said room, The claim 1 characterized by the above-mentioned. The nuclear heat utilization system according to claim 1. 8. When returning the first refrigerant from the reactor-side heat exchanger to the reactor, a part of the first refrigerant from the reactor or the first refrigerant extracted from the turbine is injected. The nuclear heat utilization system according to any one of claims 1 to 7, further comprising an injector for increasing the pressure and temperature of the first refrigerant that is returned to the nuclear reactor. 9. The nuclear heat utilization system according to claim 1, wherein a part of the first refrigerant from the nuclear reactor drives a generator to generate power.