JP2012246892A - Power generation plant using steam compressing system, and operation method thereof - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a power generation plant having a novel steam compressing system having heat efficiency higher than conventional heat efficiency and an operation method thereof, by solving the problem that the plant performance is decreased because a flow rate of a main steam being a working fluid of high pressure and low pressure turbines reduces compared to a generating steam quantity from a nuclear reactor pressure vessel or a boiler, owing to usage of high temperature main steam or extraction steam from the high pressure turbine for heating a moisture content separating superheater, in a conventional power generation plant.SOLUTION: The heat efficiency of the power generation plant is improved by overheating the main steam temperature by raising the temperature and increasing pressure of low temperature-low pressure main steam from the high pressure turbine to high temperature-high pressure main steam by small in-house power by arranging at least one steam compressor in the power generation plant. The power generation plant heat efficiency is improved by constituting a reheat cycle of the main steam by coaxially installing a main steam overheating steam compressor between the high pressure turbine and the low pressure turbine.

Description

  The present invention relates to a nuclear power plant or a thermal power plant using a steam compressor or a steam compression system.

  As a conventional power plant that uses a reactor pressure vessel 1 as a steam generation source, for example, a boiling water light water reactor (BWR) has a reactor pressure vessel 1 containing a core containing a fissile material, as shown in FIG. Water is boiled as a coolant, and the generated steam is sent to the high-pressure turbine 5 via the main steam outlet valve 2, the main steam pipe 3, and the main steam stop valve 4, and further, the main steam pipe 6 and the moisture separator (hereinafter referred to as the moisture separator). , MS) 7, moisture separation superheaters 8A and 8B, and main steam pipe 9 are sent to low-pressure turbine 10 to generate power by generator 12 linked to high-pressure turbine 5 and main shaft 11 of low-pressure turbine 10. .

  13 is an exhaust steam pipe, 15a is a seawater inlet pipe, 15b is a seawater outlet pipe, 16 is a seawater circulation pump, 19 is a water supply pipe, 42 is a main steam extraction steam from the main steam pipe 3, and 43 is a high pressure from the high pressure turbine 5. The extraction steam, 45 is the high-pressure extraction steam from the high-pressure turbine 5, and 46 is the low-pressure extraction steam from the low-pressure turbine 10.

  In a normal BWR power plant, the steam used for power generation is condensed by the condenser 14 installed on the outlet side of the low-pressure turbine 10 to become water, and then the low-pressure feed water heaters 18a to 18d and the high-pressure feed water heaters 21a and 21b. Further, the pressure is raised and heated through the low-pressure condensate pump 17 and the high-pressure feed water pump 20, and water is supplied into the reactor pressure vessel 1.

  In normal plant design, the thermal output of the core in the reactor pressure vessel is first determined, and the steam flow after the main steam pipe is optimized so that the highest thermal efficiency can be obtained with that thermal output. Specifically, when steam is converted into water by the condenser 14, the latent heat of water cannot be used for power generation and is wasted at the pressure of a normal BWR reactor pressure vessel (about 7 MPa) from the principle of thermal cycle. Therefore, a part of the main steam is extracted and the feed water is heated by the feed water heater. In this case, most of the heat of the main steam is recovered, so that the thermal efficiency of the reactor is improved.

  In general, in a BWR that uses a recirculation system having a recirculation pump and a jet pump and has an MS, the amount of steam finally sent from the outlet of the low-pressure turbine 10 to the condenser 14 is about 2 of the main steam. The remaining steam is slightly less than / 3 and about 1/3 of the remaining steam is used for heating the feed water as extracted steam. In an improved boiling water light water reactor (ABWR) in which a moisture separator superheater (hereinafter referred to as MSH) is installed in place of the MS, the steam that is finally sent from the low-pressure turbine outlet to the condenser is removed from the main steam. The amount is a little less than about 2/3 like BWR. Here, when six feed water heaters are installed, the amount of extracted steam per unit averages about 7% of the main steam.

  It is generally known to employ MSH in these BWR or ABWR power plants to improve the thermal efficiency of the plant by reheating efficiency. However, conventionally, main steam generated from a reactor pressure vessel or high-temperature extracted steam from a high-pressure turbine is used to superheat the main steam with MSH, so that main steam that is a working fluid for rotating the turbine is used. The flow rate is about 2% lower.

  Further, it is desirable that the low-temperature / low-pressure steam extra used for rotating the generator 12 by the low-pressure turbine 10 is recycled to the plant without returning to the condenser 14 to recover heat. However, from the viewpoint of pressure balance, this low-temperature and low-pressure steam has the lowest enthalpy, and it is difficult to recover energy by the usual method both in terms of pressure and temperature.

  Therefore, conventionally, a thermal power plant using a steam heat pump using a steam compressor has been proposed in order to increase the thermal efficiency of the plant. For example, Patent Document 1 discloses a thermal power in which steam supplied from a condenser is compressed by a single steam compressor, and the compressed steam is supplied from a plurality of locations in the axial direction of the steam compressor to four feed water heaters. A power plant is described.

  In the proposed thermal power plant, steam generated in a boiler is sequentially supplied to a high-pressure turbine, an intermediate-pressure turbine, and a low-pressure turbine, and power is generated by rotating a generator connected to the rotating shafts of these turbines. The steam discharged from the low-pressure turbine is condensed into water by the condenser. This water is supplied to the boiler through a water supply pipe as water supply.

  The feed water is heated by a four-stage feed water heater while passing through the feed water pipe to increase the temperature. Steam extracted from the condenser is compressed by the steam compressor and the temperature rises, and the compressed steam is extracted from a plurality of locations in the axial direction of the steam compressor and supplied to each feed water heater. The feed water is heated by the steam supplied to each feed water heater. The steam becomes condensed water in each feed water heater, and this condensed water is supplied to the feed water. Further, since the steam compressor adiabatically compresses the steam, the internal energy rises and becomes overheated. To prevent this and conserve the required power, the condensate is sprayed into the steam compressor in the form of a mist. Yes.

  Patent Document 2 describes a combined heat and steam turbine plant. This co-heat steam turbine plant supplies steam generated in a boiler to a turbine, rotates a generator to generate power, and supplies steam discharged from the turbine to a high-pressure process steam supply destination and a low-pressure process steam supply destination, respectively. . The steam supplied to the high-pressure process steam supply destination compresses the steam exhausted from the turbine with a steam compressor.

Japanese Utility Model Publication No. 1-123001 JP-A-5-65808

  Generally, in the Rankine cycle, the main steam, which is the wet steam that has finished work in the high-pressure turbine, is converted into superheated steam to improve the thermal efficiency. In other words, it is necessary to install a moisture separation superheater between the high-pressure turbine and the low-pressure turbine and adopt a reheat cycle. In order to heat the main steam, which is a fluid to be heated, in the moisture separation superheater, a part of the main steam, which is a high-temperature heat source, or extracted steam from a high-pressure turbine is used. As a result, the flow rate of the main steam that is supposed to be used for working in the high-pressure turbine and the low-pressure turbine is reduced, and the work amount is reduced accordingly.

  Therefore, the main steam that has been expanded by the high-pressure turbine into wet steam is compressed using a steam compressor to form superheated steam, and then expanded again to wet steam by the low-pressure turbine to rotate the main shaft and work on the generator. To do. As a result, the cycle efficiency can be improved by reducing the temperature of the main heat source working in the original high-pressure and low-pressure turbines by about 2% and reusing the low-temperature heat source steam that has finished work again. . For this purpose, a steam compressor may be installed on the main shaft between the high-pressure turbine and the low-pressure turbine, thereby increasing the temperature and pressure of the main steam with a small in-house power.

  In the present invention, at least one compact steam compressor is installed and connected to the main shaft connecting the high-pressure turbine, the low-pressure turbine and the generator in the power plant, particularly between the high-pressure turbine and the low-pressure turbine. The temperature of the low-temperature and low-pressure steam that has finished work is raised and increased, and then supplied to the low-pressure turbine, so that the temperature of the main steam, which is the working medium, is superheated and supplied to the low-pressure turbine. Can be improved. Furthermore, since the exhaust steam from the low-pressure turbine can be reused in the plant without discharging it to seawater in large quantities, it can be effectively used from the viewpoint of the environment. In addition, by installing a compact and high-performance steam compressor, there is no influence on other plant equipment such as a turbine building space and a piping arrangement space.

  That is, the present invention provides a nuclear power plant or a thermal power plant using a steam compression system that can improve thermal efficiency by using a heat source in the plant to convert wet steam into superheated steam with a steam compressor. With the goal.

  The present invention relates to a feed water pipe and a condensate pipe for supplying a coolant to a steam generator, a low pressure condensate pump and a high pressure feed water pump for boosting the coolant, a low pressure feed water heater and a high pressure feed water heater for heating the coolant. And a core or steam generator that heats the coolant to steam, a high-pressure turbine and a low-pressure turbine that recover energy from the steam, a generator connected to the high-pressure turbine and the low-pressure turbine by a main shaft, and a low-pressure turbine In a power plant having a condenser that cools and condenses the steam, at least one steam compressor is connected between the high-pressure turbine and the low-pressure turbine with a main shaft, and the low-temperature and low-pressure after working in the high-pressure turbine Compress wet steam to increase the temperature and pressure, and supply main steam as saturated steam or superheated steam to the low-pressure turbine to work in the low-pressure turbine. And butterflies. According to such a configuration, the main steam temperature of the wet steam, which has been lowered by the steam compressor, can be overheated, the thermal efficiency of the power plant can be improved, and the amount of exhaust heat released from the condenser to seawater can be reduced. it can.

  In the power plant, an intermediate pressure turbine is installed between the high pressure turbine and the low pressure turbine, and at least one high pressure steam compressor is connected between the high pressure turbine and the intermediate pressure turbine with a main shaft, and the intermediate pressure turbine and the low pressure turbine are connected. It is characterized in that at least one intermediate pressure steam compressor is connected and installed by a main shaft. Such a configuration can also improve plant thermal efficiency and reduce the amount of exhaust heat released to seawater.

  In the power plant, an intermediate pressure turbine is installed between the high pressure turbine and the low pressure turbine, at least one high pressure steam compressor is provided between the high pressure turbine and the intermediate pressure turbine, and at least one is provided between the intermediate pressure turbine and the low pressure turbine. One intermediate pressure steam compressor is installed by connecting at least one low pressure steam compressor with a main shaft between a low pressure turbine and a generator. Even with such a configuration, the plant thermal efficiency can be improved and the amount of exhaust heat released to seawater can be reduced.

  The power plant is characterized in that a moisture separator is installed between the high-pressure turbine and the steam compressor, and the high-pressure turbine exhaust steam is made saturated steam and supplied to the steam compressor. Such a configuration can also improve plant thermal efficiency and reduce the amount of exhaust heat released to seawater.

  Moreover, in a power plant, a moisture separation superheater is installed between the high-pressure turbine and the steam compressor, and the high-pressure turbine exhaust steam is supplied as superheated steam and supplied to the steam compressor. Such a configuration can also improve plant thermal efficiency and reduce the amount of exhaust heat released to seawater.

  In a power plant, a moisture separator superheater is installed between the high-pressure turbine and the low-pressure turbine, and the exhaust steam from the high-pressure turbine is branched from the main steam pipe and supplied to the steam compressor as a bypass flow. The superheated steam that is compressed and heated in step 1 is joined to a main steam pipe that supplies the low-pressure turbine to be supplied to the low-pressure turbine. Even with such a configuration, the plant thermal efficiency can be improved and the amount of exhaust heat released to seawater can be reduced.

  Furthermore, in a power plant, a steam compressor that uses a boiling water nuclear power plant, a pressurized water nuclear power plant or a fast breeder reactor nuclear power plant, a brackish water thermal power plant or a gas turbine combined thermal power plant is used. The power plant provided can also improve plant thermal efficiency and reduce the amount of exhaust heat released to seawater.

  According to the present invention, particularly in a nuclear power plant or a thermal power plant, wet steam that has worked in a high-pressure turbine can be reheated to high-temperature and high-pressure superheated steam by a steam compressor and supplied to the low-pressure turbine as main steam. Thus, the moisture separation superheater, which has been conventionally required, the high-pressure turbine for superheating the main steam, and the extraction steam for heating from the main steam become unnecessary, and the thermal efficiency of the power plant can be improved.

  In addition, since the steam compressor is installed coaxially on the main shaft connected to the high-pressure turbine and the low-pressure turbine, it does not require extra in-house power to rotate the steam compressor, and it has a compact configuration with a regeneration and reheat cycle. Enables improved thermal efficiency and electrical output.

1 is a system diagram of a boiling water nuclear power plant according to Embodiment 1 of the present invention. Explanatory drawing of the thermal efficiency of the boiling water nuclear power plant in Example 1 of this invention. The system diagram of the boiling water nuclear power plant in Example 2 of this invention. Explanatory drawing of the thermal efficiency of the boiling water nuclear power plant in Example 2 of this invention. The system diagram of the boiling water nuclear power plant in Example 3 of this invention. The system diagram of the boiling water nuclear power plant in Example 4 of this invention. The system diagram of the boiling water nuclear power plant in Example 5 of this invention. The system diagram of the boiling water nuclear power plant in Example 6 of this invention. The systematic diagram of the thermal power plant in Example 7 of this invention. The systematic diagram of the pressurized water nuclear power plant in Example 8 of this invention. The systematic diagram of the fast breeder reactor nuclear power plant in Example 9 of this invention. The system diagram of the combined gas turbine and thermal power plant in Example 10 of this invention. The system diagram of the boiling water nuclear power plant which is a prior art example.

  Embodiments of the present invention will be described below with reference to the drawings.

  FIG. 1 shows a system diagram of a boiling water nuclear power plant (BWR) having a steam compressor for main steam superheating according to Embodiment 1 of the present invention. The power plant includes a feed water pipe 19 for supplying coolant to the reactor pressure vessel 1, a low pressure condensate pump 17 and a high pressure feed water pump 20 for boosting the coolant, low pressure feed water heaters 18a to 18d for heating the coolant, and High pressure feed water heaters 21a and 21b, a reactor pressure vessel 1 for heating the coolant to steam, a high pressure turbine (hereinafter referred to as HPT) 5 and a low pressure turbine (hereinafter referred to as LPT) 10 for recovering energy from the steam, and HPT 5 And a generator 12 connected to the LPT 10 via a main shaft 11 and a condenser 14 that cools and condenses the steam discharged from the LPT 10.

  The high pressure feed water heaters 21a and 21b are supplied with high pressure extraction steam 45a and 45b, and the low pressure feed water heaters 18a to 18d are supplied with low pressure extraction steam 46a to 46d.

  At least one steam compressor (hereinafter referred to as SC) 30 is installed between the HPT 5 and the LPT 10, and the low temperature / low pressure main steam supplied from the exhaust pipe of the HPT 5 is adiabatically compressed to increase / decrease the temperature and pressurize the steam. Is supplied to the LPT 10 as the main steam of the superheated steam. Thereby, the main steam temperature is overheated, and the thermal efficiency is improved by strengthening the reheat cycle.

  On the other hand, in the condenser 14, in order to cool and condense the steam discharged from the LPT 10, seawater is supplied from the seawater inlet pipe 15 a into the heat transfer pipe by the seawater circulation pump 16, where heat is exchanged to the seawater outlet. It discharges into the seawater from the pipe 15b.

  In BWR, water is boiled in the core of the reactor pressure vessel 1 containing the fissile material, and steam generated by the boiling is sent to the HPT 5 and LPT 10 through the main steam pipe 3, and interlocked with the main shaft 11 of the HPT 5 and LPT 10. Power is generated by the generator 12. In a normal BWR, the steam is condensed into water in a condenser 14 installed on the outlet side of the LPT 10, and then there are six low-pressure feed water heaters 18 a to 18 d, high-pressure feed water heaters 21 a and 21 b, and low-pressure condensate. The pressure is increased and heated through the pump 17 and the high-pressure water supply pump 20, and water is supplied into the reactor pressure vessel 1.

  Generally, in BWR and ABWR, main steam and extracted steam from a turbine are used for heating feed water. Here, since six feed water heaters are installed, the amount of extracted steam per unit averages about 7% of the main steam. It has been conventionally known that when the moisture separation heater MSH is employed to improve the thermal efficiency of BWR or ABWR, the performance is improved by the reheat efficiency. However, in MSH, since the heating steam for heating the main steam is extracted, there is a problem that the main steam flow rate is reduced by about 2% and the overall plant efficiency is lowered.

  In Example 1, since MSH is not used and the main steam worked at HPT5 is directly adiabatically compressed by the steam compressor SC30 to be superheated steam, the main steam flow rate of the working fluid does not decrease, so the thermal efficiency Will improve.

  In addition, since the main shaft 11 directly connected to the HPT 5 and the LPT 10 is used to drive the SC 30, no special compressor driving force is required, and the power in the station can be small. Therefore, since a large amount of LPT extraction steam can be used for regeneration, the amount of heat exchange in the condenser 14 is reduced as compared with the conventional case, and the amount of exhaust heat is reduced to improve efficiency.

  The SC 30 adiabatically compresses the low-temperature / low-pressure exhaust steam 6 after working at the HPT 5 to increase the temperature and pressure, and supplies the main steam as the compressed superheated steam 35. At this time, the SC 30 is driven by the turbine driving force through the main shaft 11. Further, when the wetness is large on the suction side of SC30, an MS may be additionally provided. Further, when the saturated vapor is compressed on the discharge side of the SC 30 and the temperature suddenly rises and the dryness is large, it is possible to atomize fine water droplets to lower the superheat degree.

  The SC30 may use a single-stage centrifugal steam compressor that has already been developed, and these can be used in multiple stages. A multistage axial compressor may be used. SC30 is installed coaxially with the turbine in the secondary turbine building in the power plant. In Example 1, since the turbine main shaft driving force is used for the rotation of SC30, the in-house power is small, and the superheated steam can be generated by SC30 and the reheat cycle can be effectively used. Constitute.

  At this time, a plurality of SCs 30 can be arranged and used in series. For example, it is possible to increase the compression ratio at the final stage by connecting a plurality of SCs 30 in series on multiple axes. Further, the compression ratio may be adjusted by controlling the rotational speed of the control valve or SC30 so as to be the pressure in the LPT inlet.

  Usually, when the boosting ratio of the SC 30 increases, the compression work also increases, and as a result, the increased output is wasted as in-house power. In other words, even if the power generation end output improves, the power transmission end output decreases. For example, in the case of a compression ratio of 10, the in-house power ratio of all outputs by SC installation by motor drive reaches about 5% at maximum. For this reason, it is necessary to select an appropriate compression ratio and to optimize the system balance so as not to reduce the electrical output by using the increased thermal efficiency as an in-house power.

  For example, as a conventional regeneration cycle utilization system, extraction steam from HPT and LPT is used for heating feed water in a nuclear power plant, and condensed water after heating feed water uses a pressure difference from a high pressure system to a low pressure system feed water. Heat is recovered to the heater and further to the condenser. Furthermore, ABWR adopts a high pressure pump drain-up system (HPPD) and a low pressure pump drain-up system (LPPD), and each of them has thermal efficiency by regeneration cycle. Has improved.

  On the other hand, in the present invention, a system used for the high-pressure main steam system is referred to as a high-pressure steam heat-up system (HPCS) system in contrast to the above system. The present invention can also be applied to operation in a boiling water nuclear power plant or an improved boiling water nuclear power plant that is a direct type of only a primary reactor system. Therefore, the plant thermal efficiency can be improved by installing a SC between the HPT and the LPT and performing a reheat cycle without significantly changing an existing BOP system (Balance of Plant system) other than the steam supply system.

  FIG. 2 shows a schematic diagram of the thermal efficiency of the power plant according to the first embodiment. The horizontal axis represents entropy s, and the vertical axis represents temperature T. A dotted line indicates the conventional example, and a solid line indicates the first embodiment.

  First, the conventional thermal efficiency will be described with reference to the dotted line in FIG. The feed water supplied from the condenser is heated from 1 to 2 with a feed water pump or feed water heater and supplied into the reactor pressure vessel. In the reactor pressure vessel, heat is received from the nuclear fuel, and the feed water is heated from saturated water to saturated steam to change from 2 to 3. The main steam generated here is thermally expanded from 3 to 4 by HPT, and the main shaft is rotated to work.

  Here, 4 is a wet steam having a higher wetness than the saturated steam, so conventionally, the main steam is supplied to the MSH, first the wetness is removed from 4 to 5 in the MS, and then the saturated steam is obtained. From saturated steam to superheated steam from 5 to 6 in the superheater. Then, the overheated main steam is thermally expanded from 6 to 7 by LPT, and the main shaft connected to the HPT is rotationally driven to work. The low-temperature and low-pressure main steam after the completion of work is condensed in the condenser by removing heat from 7 to 1 to the seawater side.

  On the other hand, the first embodiment is different in that the main steam of the wet steam is supplied to the SC 30 and is compressed and heated in the SC 30 to be superheated steam from 4 to 6 'at a stretch. Here, conventionally, the temperature of the superheated steam is equal to or lower than the main steam temperature in the furnace, whereas in the first embodiment, the temperature is higher than the main steam temperature. Thereby, the thermal efficiency of the reheat cycle can be greatly improved.

  Moreover, there is almost no increase in in-house power by utilizing the rotational force of the turbine main shaft. In addition, it can be seen that the SC of Example 1 is configured to be more compact than the volumes of the BWR MS and ABWR MSH of the conventional example.

  FIG. 3 shows a system diagram of the power plant according to the second embodiment of the present invention. In Example 2, as shown in FIG. 3, an intermediate pressure turbine (hereinafter, IPT) 22 was installed between the HPT 5 and the LPT 10. In addition, a high pressure steam compressor (hereinafter referred to as HSC) 31 was installed between HPT 5 and IPT 22, and an intermediate pressure steam compressor (hereinafter referred to as ISC) 32 was installed between IPT 22 and LPT 10.

  The HSC 31 is vapor-compressed by a heat pump action to increase the temperature and pressure, and the temperature of the HPT5 exhaust vapor is increased and supplied to the IPT 22. In addition, the ISC 32 compresses the vapor with a heat pump to increase the temperature and pressure, and increases the temperature of the IPT 22 exhaust vapor to supply to the LPT 10. As a result, the main steam working in the HPT 5 and the LPT 10 becomes superheated steam, and the thermal efficiency can be improved by the reheat cycle.

  In this case, the HPT 5, HSC 31, IPT 22, ISC 32, and LPT 10 shown in FIG. 3 are all coaxially connected to the main shaft 11 connected to the generator 12. Therefore, since the compressor driving force can be obtained by using the driving force, the in-house power is reduced. In the following drawings, members having the same reference numerals as those in the embodiment of FIG. 1 have the same configuration unless otherwise specified.

  In Example 2, the system used for the medium-pressure main steam system is called an intermediate-pressure steam heat-up system (IPCS). This also makes it possible to improve the thermal efficiency of the BWR plant. In addition, although Example 2 used the boiling water type light water reactor plant as an example, it is applicable also to the secondary system of a pressurized water type light water reactor, and other types of nuclear power plants.

  FIG. 4 shows a schematic diagram of the thermal efficiency of the power plant as in FIG. The horizontal axis represents entropy s, and the vertical axis represents temperature T. A dotted line shows a conventional example, and a solid line shows Example 2. The performance of the conventional example is as described in FIG.

  On the other hand, in the case of Example 2, the main steam 4 of the wet steam is supplied to the HSC 31 and compressed and heated, and the main steam 4 to 6 'is heated at once to be superheated steam, and further 6' to 6 '' by the IPT 22. It is different in that it is expanded into a superheated steam from 6 ″ to 6 ′ ″ by compression heating in the ISC 32.

  Here, the temperature of the superheated steam is conventionally equal to or lower than the main steam temperature in the furnace, whereas Example 2 is heated to a temperature higher than the main steam temperature, and 6 ′ and 6 ′ ″ and HPT5 In addition, since the superheated steam can be used to perform work due to thermal expansion in the LPT 10, the thermal efficiency is greatly improved by the reheat cycle as compared with FIG. In addition, the main steam in the last stage of LPT is thermally expanded up to substantially saturated steam, so the wetness becomes shallow.

  Moreover, there is almost no increase in in-house power by utilizing the rotational force of the turbine of the main shaft. Moreover, it turns out that the vapor compressor of Example 2 becomes compact also compared with the volume of MS for BWR and MSH for ABWR of a prior art example.

  FIG. 5 shows a system diagram of the power plant according to the third embodiment of the present invention. In Example 3, in addition to Example 2 shown in FIG. 3, a low-pressure steam compressor (hereinafter referred to as LSC) 33 was installed on the downstream side of LPT 10. It is possible to increase the temperature of the exhaust steam of the LPT 10 by vapor-compressing with a heat pump at the LSC 33 to raise and raise the pressure. This also makes it possible to use exhaust heat effectively. In this case, HPT5, HSC31, IPT22, ISC32, LPT10, and LSC33 are all coaxially connected to the main shaft 11 connected to the generator 12, and can be used as a compressor driving force by using the driving force. Therefore, in-house power is reduced.

  In Example 3, a system used for the low-pressure main steam system is referred to as a low-pressure compressor steam-up system (LPCS). This also makes it possible to improve the thermal efficiency of the BWR plant. In addition, although Example 3 made the boiling water type light water reactor plant the example, it is applicable also to the secondary system of a pressurized water type light water reactor, and other types of nuclear power plants.

  FIG. 6 shows a system outline of the power plant according to the fourth embodiment. In the fourth embodiment, the MS 7 is installed between the HPT 5 and the SC 30 in the BWR power plant of the first embodiment described with reference to FIG. Thereby, the exhaust steam from HPT5 can be made into saturated steam by MS7, and can be supplied in SC30.

  FIG. 7 shows a system outline of the power plant according to the fifth embodiment. In the fifth embodiment, SH7, MSH8A, and 8B are installed between HPT5 and SC30 in the BWR power plant described with reference to FIG. Thereby, the exhaust steam from HPT5 can be supplied into SC30 as superheated steam by SH7, MSH8A, 8B.

  FIG. 8 shows a system outline of the power plant according to the sixth embodiment. Example 6 is a BWR power plant explained in FIG. 1, SH7, MSH8A, 8B are installed between HPT5 and LPT10, and the bypass exhaust steam from HPT5 branched from the main steam pipe is supplied to SC30. The compressed and heated superheated steam can be joined to the main steam pipe 9 that supplies the LPT 10 and supplied to the LPT 10. Note that the amount of bypass exhaust steam supplied to the SC 30 is adjusted by the control valves 47 and 48.

  FIG. 9 shows a system outline of a thermal power plant according to the seventh embodiment. In a thermal power plant, a boiler 1A is used as a main steam generation source. The secondary system of the power plant includes a main steam system composed of HPT5, LPT10, and SC30, and after exiting the condenser 14, a low-pressure condensate pump 17, low-pressure feed water heaters 18a to 18d, a high-pressure feed pump 20, It is the same as that of FIG. 1 that is composed of a feed and condensate system composed of high-pressure feed water heaters 21a and 21b.

  Here, in addition to the conventional configuration of the three elements HPT5, SC30, and LPT10, as shown in FIG. 5, the configuration may include a plurality of elements of HPT5, HSC31, IPT22, ISC32, LPT10, and LSC33. In this case, in the thermal power plant, the boiler 1A is a main steam generation source that generates steam. The main steam system generated in the boiler 1A is saturated steam like BWR.

  FIG. 10 shows a system outline of a pressurized water nuclear power plant (hereinafter referred to as PWR) according to the eighth embodiment. Unlike the BWR, the primary system composed of the reactor pressure vessel 1B, the primary cooling system 51, the primary cooling system circulation pump 52 and the steam generator (hereinafter referred to as SG) 50, and the main steam / feed and condensate system similar to the BWR Consists of secondary system. The main steam system in the secondary system has a steam compressor SC30. 18 is a low-pressure feed water heater, and 21 is a high-pressure feed water heater.

  Here, the secondary system may be composed of a plurality of elements of HPT5, HSC31, IPT22, ISC32, LPT10, and LSC33 as shown in FIG. 5 in addition to those composed of three elements of HPT5, SC30, and LPT10. In this case, SG50 becomes the main steam generation source instead of the reactor pressure vessel 1 of BWR.

  Example 8 can also be applied to a pressurized water nuclear power plant or an improved pressurized water nuclear power plant that is an indirect type divided into a primary system and a secondary system of a nuclear reactor.

  FIG. 11 shows a system outline of a fast breeder reactor nuclear power plant (hereinafter referred to as FBR) according to the ninth embodiment. Unlike the BWR, the reactor pressure vessel 1C, the primary cooling system 61, the primary cooling system circulation pump 62, the primary system of the intermediate heat exchanger 63, the secondary cooling system 64, the secondary cooling system circulation pump 65, and the steam generator 60 It consists of a secondary system. In FBR, sodium is used as the coolant for both the primary and secondary systems. The main steam system in the secondary system has SC30.

  Here, the secondary system may be composed of a plurality of elements of HPT5, HSC31, IPT22, ISC32, LPT10, and LSC33 as shown in FIG. Good. In this case, the steam generator 60 is the main steam generation source instead of the BWR reactor pressure vessel 1.

  Embodiment 9 can also be applied to an operating method in a fast breeder reactor nuclear power plant that is an indirect type divided into a primary reactor system, a secondary system, and a main steam system.

  FIG. 12 shows a system outline of a thermal combined power plant (hereinafter referred to as thermal C / C) according to the tenth embodiment. In this case, the air 71 sucked into the compressor 72 is compressed as the high-temperature fluid side, and the compressed air and the fuel 77 are mixed and ignited and burned by the combustor 76, and a gas turbine (hereinafter referred to as GT) 74 is used as the high-temperature gas. Inflate with. At this time, the compressor 72 and the GT 74 are connected to the main shaft 73 and rotate, and the generator 75 generates power in conjunction with the rotation.

  Further, the exhaust gas 78 obtained by rotating the GT 74 is used as a heating source, and the feed water is heat-exchanged in a waste heat recovery steam generator (hereinafter referred to as HRSG) 70 to generate main steam. The rest is the same system as the BWR main steam system and feed / condensate system. The main steam system in the secondary system has SC30.

  Here, the secondary system may be configured by a plurality of elements of HPT5, HSC31, IPT22, ISC32, LPT10, and LSC33 in addition to the conventional system including three elements of HPT5, SC30, and LPT10. In this case, instead of the BWR reactor pressure vessel 1, the HRSG 70 becomes the main steam generation source.

  In addition, as a renewable energy system, solar heat can be once stored in a regenerator and used in a Rankine cycle power plant that effectively uses natural heat energy to generate steam using this heat source.

  The tenth embodiment can also be applied to the thermal power generation that constitutes the Rankine cycle as in the case of nuclear power generation, in the thermal power plant having the high-pressure and low-pressure turbines or the operation method in the thermal power combined power plant with GT. is there.

  The present invention can be applied to nuclear power plants such as boiling water nuclear power plants and pressurized water nuclear power plants, and power plants such as thermal power plants.

DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 1A ... Boiler, 2 ... Main steam outlet valve, 3 ... Main steam piping, 4 ... Main steam stop valve, 5 ... High pressure turbine (HPT), 6 ... Main steam piping, 7 ... Moisture separation (MS), 8 ... moisture separator superheater (MSH), 8A, 8B ... moisture separator superheater, 9 ... main steam pipe, 10 ... low pressure turbine (LPT), 11 ... main shaft, 12 ... generator, 13 DESCRIPTION OF SYMBOLS ... Exhaust steam pipe, 14 ... Condenser, 17 ... Low pressure condensate pump, 18, 18a-18d ... Low pressure feed water heater, 19 ... Feed water pipe, 20 ... High pressure feed water pump, 21, 21a, 21b ... High pressure feed water heater 22 ... Intermediate pressure turbine (IPT),
30 ... Steam compressor (SC), 31 ... High pressure steam compressor (HSC), 32 ... Medium pressure steam compressor (ISC), 33 ... Low pressure steam compressor (LSC), 35 ... Superheated steam, 42 ... Main steam extraction Steam, 43 ... High-pressure turbine extraction steam, 45 ... High-pressure extraction steam, 46 ... Low-pressure extraction steam, 47 ... Control valve, 48 ... Control valve, 50 ... Steam generator (SG), 51 ... Primary cooling system, 52 ... Primary cooling System circulation pump,
60 ... Steam generator, 61 ... Primary cooling system, 62 ... Primary main circulation pump, 63 ... Intermediate heat exchanger, 64 ... Secondary cooling system, 65 ... Secondary main circulation pump, 70 ... Steam generator for recovering exhaust heat (HRSG), 71 ... air, 72 ... compressor, 73 ... main shaft, 74 ... gas turbine (GT), 75 ... generator, 76 ... combustor, 77 ... fuel, 78 ... high temperature exhaust gas

Claims (12)

A feed water line and a condensate pipe for supplying the coolant to the steam generator, a low pressure condensate pump and a high pressure feed water pump for boosting the coolant, a low pressure feed water heater and a high pressure feed water heater for heating the coolant, A core or steam generator that heats the coolant to steam, a high-pressure turbine and a low-pressure turbine that recover energy from steam supplied through a main steam pipe, and a main shaft connected to the high-pressure turbine and the low-pressure turbine. In a power plant having a generator and a condenser that cools and condenses steam discharged from the low-pressure turbine,
At least one steam compressor is installed on the main shaft between the high-pressure turbine and the low-pressure turbine, and the low-temperature / low-pressure wet steam after working in the high-pressure turbine is compressed by the steam compressor to increase the temperature. A power plant having a steam compression system that is pressurized and supplies main steam as saturated steam or superheated steam to the low-pressure turbine.   2. The power plant having the steam compression system according to claim 1, wherein an intermediate pressure turbine is installed between the high pressure turbine and the low pressure turbine, and the steam compressor includes the main shaft between the high pressure turbine and the intermediate pressure turbine. A power plant having a vapor compression system, comprising: at least one high-pressure steam compressor installed on the main shaft; and at least one intermediate-pressure steam compressor installed on the main shaft between the intermediate-pressure turbine and the low-pressure turbine. .   3. A power plant having a vapor compression system according to claim 2, wherein at least one low-pressure steam compressor is installed on the main shaft between the low-pressure turbine and the generator. .   The power plant having the steam compression system according to any one of claims 1 to 3, wherein a moisture separator is installed between the high-pressure turbine and the steam compressor, and the exhaust steam of the high-pressure turbine is saturated steam. A power plant having a vapor compression system, wherein the power plant is supplied to the vapor compressor.   The power plant having the steam compression system according to any one of claims 1 to 3, wherein a moisture separation superheater is installed between the high pressure turbine and the steam compressor, and the exhaust steam of the high pressure turbine is converted to superheated steam. A power plant having a vapor compression system, wherein the vapor compressor is supplied to the vapor compressor.   A power plant having the steam compression system according to any one of claims 1 to 5, wherein a moisture separation superheater is installed between the high-pressure turbine and the low-pressure turbine, and the exhaust steam from the high-pressure turbine is used as the main steam. A bypass branched from a pipe is provided to supply to the steam compressor, and superheated steam compressed and heated by the steam compressor is joined to the main steam pipe supplied to the low-pressure turbine and supplied to the low-pressure turbine. A power plant having a vapor compression system.   The power plant having the vapor compression system according to any one of claims 1 to 6, wherein the power plant is a boiling water nuclear power plant, a pressurized water nuclear power plant or a fast breeder reactor nuclear power plant, brackish water thermal power generation. A power plant having a vapor compression system, characterized by using either a plant or a gas turbine combined thermal power plant. A feed water line and a condensate pipe for supplying the coolant to the steam generator, a low pressure condensate pump and a high pressure feed water pump for boosting the coolant, a low pressure feed water heater and a high pressure feed water heater for heating the coolant, A core or steam generator for heating the coolant to steam, a high-pressure turbine and a low-pressure turbine for recovering energy from the steam, a generator connected to the high-pressure turbine and the low-pressure turbine by a main shaft, and the low-pressure turbine In a method of operating a power plant having a condenser that cools and condenses discharged steam,
A power plant having a vapor compression system, wherein the low-temperature / low-pressure wet steam after working in the high-pressure turbine is compressed, heated and pressurized, and supplied to the low-pressure turbine as saturated steam or superheated steam. Driving method.   The operation method of a power plant having a vapor compression system according to claim 8, wherein the exhaust steam of the high-pressure turbine is made saturated steam and supplied to the steam compressor. Method.   The power plant having a steam compression system according to claim 8 or 9, wherein the exhaust steam of the high-pressure turbine is converted into superheated steam and supplied to the steam compressor. Driving method.   11. A method for operating a power plant having the steam compression system according to claim 8, wherein the exhaust steam from the high-pressure turbine is branched and supplied to the steam compressor, and the compressed and heated superheated steam is supplied to the low-pressure turbine. A method for operating a power plant having a vapor compression system.   12. A method for operating a power plant having the vapor compression system according to claim 8, wherein the power plant is a boiling water nuclear power plant, a pressurized water nuclear power plant, a fast breeder reactor nuclear power plant, brackish water. A method for operating a power plant having a vapor compression system, characterized by using either a thermal power plant or a gas turbine combined thermal power plant.

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