RU2253917C2 - Mode of exploiting of an atomic steam-turbine plant and an installation for executing it - Google Patents

Abstract

FIELD: atomic technique and heat-exchanging engineering.

SUBSTANCE: in the mode of exploiting of an atomic steam-turbine plant the steam which is going out of a hot-water generator is pressed to get higher pressure at least in one for example in a multi-stage compressor primarily with cooling off its stages with feed water of an installation. The atomic steam-turbine plant has corresponding equipment for execution of declared mode of exploitation. The invention allows to increase efficiency of a single electric( and outlet thermal} power of operating and newly built atomic steam-turbine plants producing with nominal evaporative capacity of their reactor installations of electricity for atomic electric power stations and at necessity of thermal power for atomic thermoelectric power stations. At that besides summary economy of used nuclear and organic fuel and also of reducing summary capital expenditures on building stations improving main index of total effectiveness of electric or thermal stations would be achieved.

EFFECT: reduces cost of an established kilowatt of the energetic installation.

6 cl, 3 dwg

Description

The invention relates to the field of nuclear engineering and heat energy, is aimed at improving energy-saving technologies and can be used in combined nuclear steam turbine power plants, in which for consumers due to the rational use of the best achievements of modern nuclear technology and energy turbine construction with high efficiency of using nuclear and non-nuclear (organic) fuels are produced electric and, if necessary, also thermal energy.

There is a method of operating an atomic steam turbine power plant, in which the feed water compressed by a pump is passed through the sides of the steam generators of a power plant (EU) heated by primary (for example, water), which produce at least saturated water vapor from the heat of a nuclear reactor, which is then sent to work in a steam turbine rotating an electric generator (see, for example, the book "Nuclear Power Plants", T.Kh. Margulova, M., "Higher School", 1974, p.20.21, Fig. II.I b, p. 38, 172).

At the same time, the following drawback is inherent in this method of operating EU, limiting their overall profitability. As you know, the thermal efficiency of nuclear power plants and nuclear power plants is characterized by the values of efficiency and specific heat consumption. The main indicators of the overall profitability of power plants, including nuclear ones, are the specific capital costs of their construction and the cost of electricity supplied. The specific capital costs in rubles (or dollars) are called the cost of the installed kilowatt K _mouth = K _article / W _el. ,

where K _article - the total cost of the power plant, rubles (dollars),

W _el. - installed electric power of the power plant, kW el.

The cost of the installed kilowatt substantially depends on the type of station, the parameters of the steam and coolant, the unit capacity of the reactor, turbogenerators, steam generators and other devices, as well as the total capacity of the station (see, for example, the aforementioned book by T.Kh. Margulova on page 52).

For stations of the same type and parameters, an increase in the unit power of the units and the power of the station as a whole leads to a decrease in the cost of the installed kilowatt (e). The smallest values of K _{mouth are} achieved at power units with a capacity of 300-500 MW (e) and more.

The development of the power system is in the direction of increasing unit capacities, block design of the steam generator and steam turbine, as well as by increasing the parameters (pressure and temperature) of the working steam of the steam turbine part (PTC) of the electric power plant. The first two allow you to reduce the cost of the installed kilowatt by reducing the unit cost of equipment and reducing the dimensions of the installation and the volume of buildings, enlarging auxiliary equipment and reducing the cost of installation. An increase in steam parameters (pressure and temperature) at any thermal station, including a nuclear one, always leads to an increase in the efficiency of the station, on which fuel consumption depends.

The thermal efficiency of nuclear power plants is not yet great, but for stations with water-cooled nuclear reactors it is the smallest and, in essence, cannot be significantly increased (see the above book by T.Kh. Margulova on page 175).

This is due to the fact that the thermal efficiency of the Rankine cycle in such nuclear power plants reaches its maximum value at primary water pressures of 165-170 kg / cm ² and then decreases. A saturated vapor pressure of the order of 70 ata (T _us = 284 ° C) corresponds to the highest critical heat flux, which is observed for all substances at pressures of about 1/3 of the critical temperature, as well as the fuel cladding temperatures acceptable for zirconium alloys. In this regard, the maximum effective electric efficiency of the best double-circuit water-cooled nuclear power plants of VVER-1000 is relatively small and does not exceed 33-35%, which is noticeably inferior to the efficiency of thermal power plants (TPPs), the steam turbines of which operate at increased conjugate initial parameters of steam.

To further increase the efficiency of steam turbine nuclear power plants, it is necessary to increase the pressure and temperature of the steam sent to the steam turbine. At the same time, we note that the initial parameters of steam at which the humidity of the steam in the last stage of the turbine in order to avoid erosion of the blade apparatus by water drops does not exceed the permissible value of 12-13% are called the conjugate initial parameters. Moreover, if the initial temperature of the steam is lower than the conjugate (by pressure), then an intermediate superheating of the steam is necessary.

To eliminate the aforementioned drawback, a method of operating an atomic steam turbine power plant is known, according to which feed water compressed by a pump is passed through the heated sides of steam generators of a steam generator heated by primary heat carrier, which convert feed water into water vapor, which is then heated in special overheating channels of a nuclear reactor and then they are sent to perform a work in a steam turbine rotating an electric generator of a power unit (see, for example, the book "Atom power stations ", T.Kh. Margulova, M.," Higher School ", 1974, pp. 172, 178-180).

However, the disadvantage of this method, also limiting its cost-effectiveness, is that a further increase in steam parameters (for example, more than 90 ata and 480 ° C) is impossible without intermediate superheating of the steam, the organization of which in the nuclear reactor creates even greater difficulties, since it decreases the vapor density and, accordingly, the heat transfer coefficient of nuclear heat from the fuel rods to it decreases. Moreover, if the initial superheating of steam for a pressure of 90 atm and above is feasible in a reactor, then for pressures of 30-40 ata (which are obtained after the release of sharp steam from high-pressure cylinders of modern steam turbines with superheated steam, it cannot be performed as nuclear (for the same reasons as intermediate overheating), including even in channel type reactors.

The presence of steam overheating, especially nuclear, at first glance should be considered preferable. However, for nuclear power plants, an efficiency indicator, as indicated earlier, is not only thermal efficiency, but also the burnup rate of nuclear fuel. These two most important indicators are always interconnected, but under certain conditions, in particular, in the event of overheating of the steam, they conflict. So, the use of nuclear overheating, appropriate from the point of view of increasing the efficiency of the station, in the current state of reactor material science requires the use of stainless steel overheating fuel rods for cladding. As a result, there is a loss of neutrons in shell materials in fast reactors, plutonium production is reduced and the burnup depth achieved, does not compensate for the gain in thermal efficiency.

It is likely that nuclear overheating could become more widespread after the creation of cladding of fuel rods with a small neutron absorption cross section suitable for elevated temperatures. Existing zirconium alloys with a maximum temperature of use of 360 ° C allow only a slight superheating of the steam with an initial pressure of 65-70 at. This achieves a decrease in steam humidity in the steam distribution organs and the initial stages of the steam turbine, which can slightly increase the reliability of operation of the nuclear power plant.

We can assume that nuclear overheating will find widespread only after the creation of zirconium alloys suitable for high temperatures. The currently used alloys allow only slightly to overheat steam with an initial pressure of 65-70 atmospheres. Therefore, there has recently been a tendency to use, albeit insignificantly, nuclear overheating in single-circuit nuclear power plants (see, for example, the book “Nuclear Power Plants”, T.Kh. Margulova, M., “Higher School”, 1974, p. 180). Therefore, atomic steam turbine power plants operated by the above known methods do not differ in high efficiency neither at present nor in the near future.

The aforementioned drawbacks are deprived of the known method of operating an atomic steam turbine power plant, according to which, in a reactor plant (RU), the water compressed by a feed pump is converted, mainly from a steam generator, into a carrier of thermal energy — water vapor, which is subsequently heated to at least , one superheater, the heating side of which serves for combustion, mainly gaseous or liquid organic fuel, as well as an oxidizing agent in the form of, for example, atmospheric air, and then superheated steam of the paired parameters are sent to the unit’s rotating turbine to perform work in a rotating electric generator, equipped with, among other things, surface regenerative feed water heaters, which are obtained in the condenser of the steam-turbine part (PTC) of the unit (see, for example, the book “Atomic electric stations ”, T.Kh. Margulova, M.,“ Higher School ”, 1974, pp. 209-210).

A nuclear steam turbine power plant for implementing this method of operation may include a reactor unit that produces a carrier of thermal energy - water vapor (the working fluid of the PTC unit), and a steam turbine unit including a heated side of a steam generator and a heated side connected by pipelines to the reactor installation for steam and feed water of at least one superheater of water vapor, the heating side of which is connected through a locking control device to source of gaseous or liquid fossil fuels, as well as, for example, through a gas blower with atmospheric air for burning fuel, a steam turbine driving an electric generator, a condenser, a condensate pump, a deaerator, a feed pump, and also mainly surface regenerative feed water heaters.

However, this method of operating nuclear power plants, in turn, has an important drawback that limits the efficiency of the entire nuclear power plant, since increased conjugate initial parameters of fresh steam at an initial pressure of 65-70 atm are realized by only limited “organic” heating of the steam leaving the steam generators EU. This is due to the fact that in order to obtain higher conjugate initial parameters of steam from GHGs with an initial pressure of 70 atm (for light-water reactors), steam can be heated to a temperature of no higher than 450 ° C (and not, for example, 500 ... 600 ° С), that is, to obtain the associated parameters known for steam pressure of 65-70 ata - 70 ata / 450 ° С (see, for example, the book “Nuclear Power Plants”, T.Kh. Margulova, M., “Higher School ”, 1974, p. 177). This is due to the fact that the conjugate initial parameters at an initial pressure of 70 ata are 70 ata / 450 ° C and therefore further heating of the steam at this pressure is simply ineffective. Therefore, the further development of this method of generating electricity at combined nuclear power plants has not received, in particular, in the USA further development because the indicated conjugate parameters only slightly (i.e., only 3-4% relative) increase the effective electrical efficiency of nuclear power plants with additional material costs for the introduction of means for heating steam with organic fuel. That is, the effective electrical efficiency of such an improved dual-circuit water-water NPP will not exceed ~ 36%.

The maximum initial parameters of fresh steam for nuclear power plants have now been obtained in nuclear power plants with a liquid metal, sodium coolant (see, for example, IAEA materials "Status of liquid metal cooled fast reactor technology" IAEA-TECDOC-1083, April 1999, p. 442 -443.452, as well as the book "Nuclear Power Plants", T.Kh. Margulova, M., "Higher School", 1974, pp. 20-22, 342, 348, 350, Fig. II.I g). For example, in NPPs with a fast sodium reactor BN-800 with the initial parameters of superheated steam of 140 ata and 490 ° С, the effective efficiency of nuclear power plants is 38%, and in NPPs of BN-600 with the initial parameters of superheated steam of 140 ata / 505 ° С the effective efficiency of nuclear power plants makes up 39.5-40.8%.

The maximum temperature of the superheated steam of these nuclear power plants is determined by the maximum temperature (525 ° C) of heating sodium and is unlikely to be significantly increased in the near future. And the theoretically possible increase in the pressure of superheated steam by the feed pump over 140-210 ata will not increase, but will reduce the thermal efficiency of nuclear power plants, as these parameters will not correspond to the conjugate initial parameters of fresh steam known in heat engineering (see, for example, the book "Heat Power Engineering and Heat Engineering" General Issues. Handbook, edited by V. A. Grigoriev and V. M. Zorin, M., "Energy" , 1980, p. 344). Therefore, a further increase in efficiency even for the most advanced high-temperature sodium nuclear power plants is very problematic.

This is due to the well-known fact (see, for example, the book "Thermal Power Plants", V.Ya. Rogozhin, M., Energoatomizdat, 1987, p. 32-53) that the simultaneous increase in the initial temperature is most thermodynamically effective and initial steam pressure.

We give the conjugate initial steam parameters corresponding to a final steam humidity in the turbine of 13% and an internal relative turbine efficiency of 0.85:

That. ° C ... 600 570 540 515 480 450 410 Ro, MPa 20 eighteen 14 12 nine 7 5

Intermediate superheating of the steam allows, while maintaining the recommended initial steam temperature of 540-560 ° C, to bring additional heat to the working steam, to increase its operability and efficiency of the turbine unit and power plant.

At the same time, intermediate superheating of the steam allows, using a limited initial temperature and a given permissible final humidity of the steam, to increase the initial pressure in excess of its conjugate value, which also contributes to an increase in the efficiency of the turbine plant and power plant.

Here, at what conjugate initial parameters of fresh steam do modern domestic steam turbines (LMZ - St. Petersburg, TMZ - Yekaterinburg) operate economically (see, for example, the book "Steam Turbines", A.V. Scheglyaev, M., Energoatomizdat, 1993 city, book 1 - p. 76-98, book 2 - 188-206):

130 ata / 540 ° C / 540 ° C (efficiency factor (gross) = 41.8-44.6%, excluding own energy costs of technical training colleges),

180 ata / 540 ° C / 540 ° C (Efficiency (gross) = 46.5%),

240 ata / 540 ° C / 540 ° C (Efficiency (gross) = 46.8%).

According to the article "On the improvement of power units and their steam turbines and the transition to a new level of steam parameters" of the journal "Heat Power Engineering", No. 12, 1994, pp. 43-50 in 1992-1998. abroad - in Germany, Japan, Denmark and the Netherlands, the most advanced organic (coal, including gasified, or natural gas) TPPs with a capacity of 400 to 800 MW el., technical vocational schools of which, in order to increase the efficiency of TPPs, were put into operation , work on the following extremely achievable in the energy sector increased conjugate initial parameters of steam:

250 ata / 558 ° C / 560 ° C, at which el. Efficiency gross = 51.4%, and email. Net efficiency = 45.3%,

280 ata / 580 ° C / 560 ° C, at which el. Net efficiency = 45.0%

290 ata / 580 ° C / 580 ° C / 580 ° C, at which el. Net efficiency = 47.0%.

At the same time, steam turbine units for the mentioned TPPs are manufactured by such reputable western companies as Siemens, ABB, Toshiba, Mitsubishi, DEK, Alstom, MAN and General Electric. the aforementioned article also notes that currently the technology and materials of technical colleges for the maximum steam temperature of 593 ° C are mastered, and in the near future economically more profitable maximum steam temperatures of 621 ° C and 641 ° C with the corresponding supercritical conjugate vapor pressures will be mastered.

Thus, it can be seen from the foregoing that in the well-known methods of operating existing atomic steam-turbine power plants, it is practically impossible to achieve the maximum initial steam parameters achieved in organic thermal power engineering that provide the highest cost-effectiveness and unit power of combined nuclear power units producing electric and, if necessary, thermal energy.

In connection with the stated problem, the claimed technical solution is aimed at solving this problem, it is to increase the efficiency and unit electric power of the existing atomic steam turbine power plants that produce electric power (NPP) and, if necessary, thermal energy, with the nominal steam capacity of their reactor plants (APEC). At the same time, an improvement will be achieved in the main indicator of the overall cost-effectiveness of power plants or thermal power plants, namely: reduction in the cost of the installed kilowatt (e) of power plant.

To solve this problem, in a known method of operating an atomic steam turbine power plant, in which in a reactor plant (RU) due to the heat of nuclear fuel, the water compressed by the feed pump is converted, mainly, in a steam generator into a carrier of thermal energy - water vapor, which is subsequently heated to at least one superheater, to the heating side of which serves for combustion, mainly gaseous or liquid organic fuel, as well as an oxidizing agent in the form of, for example, atmospheric air a, and then the superheated steam of the paired parameters is sent to the steam turbine of the installation, to be equipped with, among other things, surface regenerative heaters of feed water, which is obtained in the condenser of the steam-turbine part (PTC) of the installation, for the work to be performed in the rotating electric generator, the water vapor coming out of the steam generator is compressed to more high pressure in at least one, for example, a multi-stage compressor, mainly with intermediate cooling of its stages by the feed water of the installation.

At the same time, the water vapor spent in the high-pressure cylinder (CVP) of the steam turbine is heated in the heated side of at least one superheater, to the heating side of which, for the most part, gaseous or liquid organic fuel and an oxidizing agent in the form of atmospheric air are fed, after which the superheated water vapor is sent further along the standard path of the cylinders of the steam turbine of the power plant.

In addition, the feed water is compressed by the feed pump to the maximum pressure at the inlet of the steam generator, which, at nominal thermodynamic parameters of the heating medium coolant, ensures the water is converted into steam in the heated sides of the installation’s steam generator, resulting in the combined compression of the resulting steam and its additional compressor heated in one or two intermediate superheaters of a steam turbine get higher conjugate initial parameters of the steam, which provide They provide more economical operation of the steam turbine part of the installation and the power installation as a whole.

At the same time, the water vapor compression compressor is rotated by the steam turbine of the power plant or the secondary gas turbine power plant (GTU) rotating the second electric generator, the combustion chamber of which runs on organic fuel, and the exhaust gases of the gas turbine are directed to the heating side of the heat exchanger-recuperator, which provides the consumer with hot water during the heating season or steam from the heated side of the heat exchanger-recuperator.

In addition, during periods of shutdown (for example, during scheduled reloading of nuclear fuel) of the nuclear reactor and / or shutdown of the steam turbine part of the installation, electrical and, if necessary, thermal energy is generated by the operation of the gas turbine power plant (GTU), the shaft of which is mainly disconnected when this from the shaft of the compressor compressing water vapor.

At the same time, in a nuclear steam turbine power plant, including a reactor plant (RU), producing a carrier of thermal energy - water vapor (the working fluid of the PTC plant), as well as a steam turbine plant including piping to the reactor plant for steam and feed water, including the heated side of the steam generator, heated side of at least one superheater of water vapor, the heating side of which is connected through shut-off and control devices to a source of gaseous or liquid organic fuel, as well as, for example, through a gas blower with atmospheric air for burning fuel, a steam turbine driving an electric generator, a condenser, a condensate pump, a deaerator, a feed pump, and also, mainly, surface regenerative feed water heaters, the output of water vapor from the heated side of the steam generator of the switchgear is connected through shut-off devices simultaneously with the steam inlet to the multistage polytropic, feedwater-cooled compressor, driven or steam tour another, or gas turbine power plant (GTU), the combustion chamber of which is made with the possibility of heating with gaseous or liquid organic fuel, and is also connected to the steam inlet to the medium-pressure working cylinder (CSD) of the steam turbine and to the steam inlet, a superheater, which, in turn, is connected to the central cylinder of the steam turbine, while the output of the compressed water vapor from the polytropic compressor is connected to the steam inlet to the high pressure cylinder (CVP) of the steam turbine through the heated side of the superheater, and d of exhaust gas from a gas turbine gas turbine, which drives a steam compressor and a second generator of the installation, is connected to the heating side of the heat exchanger-recuperator, the heated side of which is simultaneously connected through shut-off devices to the compressed air outlet from the gas turbine compressor, with the heated air entering the gas turbine combustion chamber , as well as with the circulation circuit of the consumer of thermal energy.

In addition, the shaft sections of the steam turbine between the high and medium pressure cylinders, as well as the shaft section between the steam compressor and the gas turbine installation, can be equipped with couplers, which allow connecting or disconnecting these shaft sections, including, for example, while the shafts are running.

The essence of the invention is illustrated by drawings, which depict:

- figure 1 - schematic thermal diagram (PTS) of the proposed power plant according to option 1 performance, mainly for power plants;

- figure 2 is a typical I-S diagram of the upper part of the thermodynamic cycle of work of options 1 and 2 versions of the claimed invention for a power plant with a water-cooled nuclear reactor;

- figure 3 is a schematic thermal diagram (PTS) of the proposed power plant according to embodiment 2, mainly for a cogeneration plant.

- Given that the essence of the proposed method of operating nuclear power plants relates, in practice, only to improving the operation of the steam turbine part of nuclear power plants, the presented drawings do not show single-circuit nuclear power plants, including single-circuit pressurized water-cooled reactor plants that produce water vapor for technical training colleges (see, for example, the book “Nuclear electric nuclear power plants”, T.Kh. Margulova, M., “Higher School”, 1974, p. 20, Fig. II.I a, b, d), and also the well-known three-circuit ones, for example, are not shown sodium reactor plants.

Note: it may be noted that such terms as known in heat engineering as “heated or heating sides of surface (recuperative) heat exchangers in the form of, for example, steam generators, heaters, etc., are used, for example, in such a Russian patent as“ Operation method combined-cycle power plant and installation for its implementation ”(patent No. 2166102).

The proposed method of operating an atomic steam turbine power plant producing electric and thermal energy is carried out in the following sequence.

The steam released from the steam generator (or reactor installation) is compressed to a higher pressure in at least one, for example, multi-stage compressor, mainly with intermediate cooling of its stages by the plant’s feed water.

At the same time, the water vapor spent in the high-pressure cylinder (CVP) of the steam turbine is heated in the heated side of at least one superheater, to the heating side of which, for the most part, gaseous or liquid organic fuel and an oxidizing agent in the form of atmospheric air are fed, after which the superheated water vapor is sent further along the standard path of the cylinders of the steam turbine of the power plant.

In addition, the feed water is compressed by the feed pump to the maximum pressure at the inlet of the steam generator, which, at nominal thermodynamic parameters of the heating medium coolant, ensures the water is converted into steam in the heated sides of the installation’s steam generator, resulting in the combined compression of the resulting steam and its additional compressor heated in one or two intermediate superheaters of a steam turbine get higher conjugate initial parameters of the steam, which provide They provide more economical operation of the steam turbine part of the installation and the power installation as a whole.

At the same time, the water vapor compression compressor is rotated by the steam turbine of the power plant or the secondary gas turbine power plant (GTU) rotating the second electric generator, the combustion chamber of which runs on organic fuel, and the exhaust gases of the gas turbine are directed to the heating side of the heat exchanger-recuperator, which provides the consumer with hot water during the heating season or steam from the heated side of the heat exchanger-recuperator.

In addition, during periods of shutdown (for example, during scheduled reloading of nuclear fuel) of the nuclear reactor and / or shutdown of the steam turbine part of the installation, electrical and, if necessary, thermal energy is generated by the operation of the gas turbine power plant (GTU), the shaft of which is mainly disconnected when this from the shaft of the compressor compressing water vapor.

Variant 1 of execution of the atomic steam turbine power plant according to the claimed invention is intended mainly for power plants and consists of the following basic units of equipment combined by corresponding pipelines or cavities of hull structures (see figure 1).

For individual stages of the technological process, all thermal power equipment of a nuclear power plant (ATEC) is divided into reactor, steam turbine and condensation units and a condensate-feed path. In a sealed reinforced concrete building of the reactor compartment (or reactor installation 1) of a nuclear power plant, mainly inside a steel safety housing or containment shell 2, there are a nuclear reactor 3, steam generators 4 and circulation pumps 5 connected to each other along a first (e.g. water) loop.

The steam turbine and condensation unit, together with the superheaters and the feed-and-feed path, are located in another separate, mainly sealed building of the steam turbine section of the NPP or ATEC (this building is not shown in the drawing).

Nuclear reactor 3 is used only for energy-intensive (1517 kJ / kg at 285 ° C and 65 ata) vaporization of the working fluid of the steam-turbine part of the installation with the temperature and pressure of the steam produced that are maximally achievable for the nuclear water-water cycle. The output of water vapor from the heated sides of the steam generators 4 is connected via a shut-off device 6 to the steam inlet to the first or only multistage polytropic compressor 7, driven by a steam turbine, consisting, for example, of a coaxial high-pressure cylinder (CVP) 8, a medium-pressure cylinder (DPS) ) 9 and a low-pressure cylinder (LPC) 10 and a driving electric generator 11. For the quick connection-disconnection of the shaft section of the steam turbine between the CVP 8 of the DSP 9, a connecting (or coupling) coupling 12 is installed.

At the same time, the outlet of water vapor from the heated sides of the steam generators 4 is connected by a pipeline through the locking device 13 to the DAC 9, and also through the locking device 14 is connected to the DDS 9 through the heated side of the organic superheater 15. The output of the compressed water vapor from the compressor 7 is connected by a pipeline to the steam inlet to the CVP 8 through the heated side of the organic superheater 16, and the heating sides of each superheater 15 and 16 are connected to their inputs through shut-off and control devices 17 and 18 with sources azoobraznogo or liquid organic fuels, as well as the inputs to the heating side superheater 15 and oxidant 16 - atmospheric air supplied to gas blowers, which in Fig. not shown. In addition, the output of water vapor from the DDS 9 of the steam turbine can be connected to the steam input to the low pressure cylinder 10 of the steam turbine through the heated side of an additional organic superheater, which is to hell. not shown.

The outputs of the combustion products of organic fuel from superheaters 15 and 16 are connected to the heating side of at least one waste heat boiler 19, the heated side of which is made in the form of a heat exchange circulation loop containing a pipe system 20, a network water pump 21 and a shut-off device 22.

The steam output from the low pressure cylinder 10 of the steam turbine is connected to the cooled side (or cavity) of the condenser 23, which is then connected to the condensate pump 24. The heat transferred to the cooling water in the condenser is irretrievably lost. In this regard, the loss can be reduced by reducing the flow of steam into the condenser, which is achieved by directing part of the steam from the steps of the steam turbine to regenerative low-pressure feed water heaters (HDPE) 25 and 26, as well as to high-pressure regenerative feed water heaters (LDPE) ) 27 and 28. To automatically maintain the oxidation-reduction potential of the power plant’s feed water, the steam condensate exits from the LDPE 27, 28 are connected to a deaerator 29, in the lower tank of which at a pressure above atm Sphere creates a certain supply of water. The outlet of the feed water from the feed tank of the deaerator 29 is connected through the feed valve 31 to the heated sides of the LDPE 27, 28 and then to the heated sides of the steam generators 4 of the power plant.

To provide the consumer with thermal energy, steam withdrawals from the DAC 9 of the steam turbine are connected to the heating sides of the network heat exchangers 32 and 33, the heated sides of which are connected by pipelines to the water heating system circulated by the network pump 34. To reduce the mechanical costs of the required water vapor compression by a multistage compressor 7 compressor stages are interconnected through the annular cavities of heat exchangers 35, 36, through the tubes of which cooled feed water is pumped from ka PND 25, 26 to the deaerator 29.

The characteristic points of change in the physical state of the working fluid of the steam-turbine part of the nuclear power plant (inputs and outputs from the main elements of the plant) are marked in Fig. 1 with the letters a, b, c ..., h, f. The same letters in figure 2 indicate the corresponding characteristic points I-S diagrams of the thermodynamic cycle of water vapor for domestic serial steam turbines, for example, K-310-23,5-3; T-250 / 300-23.5; K-800-23.5 with supercritical conjugate initial steam parameters of 240 ata / 540 ° C / 540 ° C as applied to steam generators of a dual-circuit nuclear steam-turbine power plant.

In this case, on the I-S diagram of figure 2, the following notation is indicated:

Qяp - heat (specific) supplied to the feed water of the second circuit in the steam generators 4 from the nuclear reactor 3;

Qп1 - heat supplied to the compressed water vapor of the 2nd circuit from the organic fuel of the superheater 16;

Qп2 - heat supplied to the water vapor of the 2nd circuit from the intermediate superheater 15;

X is the degree of dryness of water vapor;

Qк is the heat given off by the 2nd circuit of the AEU in the capacitor 23.

In addition, in the diagram:

- the PTU cycle (its upper part), now used in traditional steam turbine nuclear power plants and at nuclear power plants with light-water nuclear reactors, is represented by the dash-dot line "a-f";

- the above-mentioned prototype known thermodynamic combined cycle of “fire” steam overheating without prior compression by the compressor is shown in the diagram by the dashed line “a-h-f”;

- proposed according to the claimed invention, the thermodynamic cycle to increase the efficiency and power of a nuclear steam turbine power plant is represented in the diagram by solid lines "a-b-c-d-e-f".

From the IS diagram shown in FIG. 2, it is clearly seen that the proposed method for generating electricity and heat in combined power plants is noticeably superior in terms of economy and power by the increase in the closed-loop area of a nuclear power plant or nuclear power plant, as well as a significant increase in the average temperature of heat supply to the working fluid of the cycle traditional and well-known combined nuclear power plants (APEC).

The embodiment 2 of the nuclear steam turbine power plant, implemented according to the claimed invention, mainly for combined nuclear power plants (KATEC), shown in Fig. 3, has the following main differences from the power plant option 1, the thermal diagram of which is shown in Fig. 1.

In this embodiment of the power plant, the rotation of the multi-stage polytropic steam compressor 7 is performed using an additional, predominantly serial gas turbine unit (GTU) 37, rotating an additional electric generator 38 (for domestic serial GTUs see Journal of Heat Power Engineering, No. 9, 1992, p. 2 -5). To connect-disconnect (right on the go) the shafts of the steam compressor 7 and the shaft of the gas turbine 37, a coupling 39 is installed. The gas turbine 37 is arranged as follows. The outlet of the compressor 40 suctioning atmospheric air is connected through a shut-off device 41 to the heated side of a heat exchanger-recuperator 42, which is connected through a shut-off device (fittings) 43 to a gas turbine heater - a combustion chamber 44, to which gaseous or liquid organic fuel is directed via a shut-off-control device 45 . In addition, the compressor 40 and the combustion chamber 44 are interconnected bypass bypass heat exchanger-recuperator 42 with a shut-off device 46.

The heated GTU working fluid exit from the combustion chamber 44 is connected to a gas turbine 47, which drives compressors 7 and 40, as well as an electric generator 38, which in the start-up mode of a gas turbine can operate as a starting electric motor for these compressors and a turbine. To quickly provide emergency electricity to the emergency de-energized circulating pumps 1 of the reactor circuit, the gas turbine unit 37 can also be equipped with a starting carburetor or diesel internal combustion engine, which is not shown in the drawings. The outlet of the gas turbine engine 37 from the gas turbine 47 is connected to the exhaust gas inlet to the heating side of the heat exchanger-recuperator 42, the gas outlet from which is connected to the atmosphere. To ensure the transfer of heat to the consumer from GTU 37, the gas inlet and outlet from the heated side of the heat exchanger-recuperator 42 are connected via shut-off elements 48, 49 to the circulation circuit of the heat consumer, which also includes a network circulation pump 50 and a drain shut-off device 51.

In addition, in this embodiment, the EU output of feed water from the feed valve 31 is connected through a shut-off element 52 with the water inlet to the heated sides of the LDPE 27, 28, as well as bypass pipe 53 through a shut-off device 54 and a heated side of the organic economizer heater 55 with an input feed water to the heated sides of the steam generators 4 EU. In this case, the heating side of the heater 55 is connected through a shut-off-regulating device 56 to a source of gaseous or liquid organic fuel, as well as to a source of oxidizing agent - atmospheric air, for example, to a gas blower, which is to hell. not shown.

To provide the consumer with additional thermal energy, the bypass pipe 53 is connected via a shut-off device 57 to the outlet of the feed water from the last LDPE 28 before connecting it to the heater 55.

A circulation loop is connected to the sections of the feed water path entering the LDPE 27 and leaving the LDPE 28 and located between the locking member 52 and the LDPE 27, and also between the locking member 57 and the LDPE 28 through the locking devices 58, 59 to the heated sides of the LDPE 27, 28 thermal energy consumer, including a network pump 60.

The I-S diagram of the thermodynamic cycle of water vapor of this embodiment of the claimed EU also corresponds to the I-S diagram depicted in figure 2.

Two of the above options for the implementation of the inventive atomic steam turbine power plants operating according to the proposed method of operation, work as follows.

OPTION 1

This embodiment of the proposed atomic steam turbine power plant (see figure 1) is preferred for power plants that provide heat to their own consumers.

As already indicated, in order to save the work of compressing a steam compressor, the fuel of a nuclear reactor 3, for example, water-water type VVER-1000, is used in this EA primarily for energy-intensive (1517 kJ / kg at 284 ° C and 65 ata) steam generation (that is, the conversion of water into steam) of the working fluid of the steam turbine part (PTC) of a power plant with the maximum pressure and temperature of the steam leaving the steam generators 4 (or from a single-circuit water-water nuclear reactor) of the reactor installation (see .. point "a" in the diagram of figure 2). At the same time, a multi-stage polytropic compressor 7 (as polytropic compression of gases and vapors is known to be the only practical compression cycle in contrast to the purely theoretical isothermal and adiabatic compression of gases and vapors) is launched by an electric generator 11 operating during this period, a starting electric motor CVP 8, CSD 9 and TsND 10 of a steam turbine of a power plant are also being commissioned.

The locking device 6 is open, and the locking device 13, 14 is closed. As a result of the operation of compressor 7 cooled by feed water in heat exchangers 35, 36, steam emitted from EI steam generators 4, for example, is compressed at a pressure of 65 atm and a temperature of 290 ° C to the required high pressure, for example (see line “a-b” on the diagram of figure 2) to 240, 180 or 130 ata. Next, the compressed water vapor is directed to the heated side of the first superheater 16, where, due to the heat of combustion of a gaseous or liquid organic fuel mixed with atmospheric air, it is heated to a temperature corresponding to a higher pressure value and therefore economical conjugate initial steam parameters (for example, to 540 ° C at 240 ata; see line “bc” in the diagram of FIG. 2).

From the superheater 16, high-temperature compressed water vapor is supplied to the high pressure cylinder (CVP) 8 of the steam turbine, where, as a result of the loss of part of its internal energy, it expands (for example, to 40 ata) and cools, for example, to 330 ° C (see line “cd” in the diagram of figure 2). After the exhaust steam exits from CVP 8, this water vapor is supplied for intermediate overheating to the heated side of the second superheater 15, in which, due to the heat of combustion of gaseous or liquid organic fuel, it is heated at a pressure of 40 atm again to a temperature value of 540 ° C conjugated to this intermediate pressure ( see the “de” line in the diagram of FIG. 2), then this steam, according to the standard scheme, is sequentially triggered in the DSP 9, the low pressure cylinder 10 and finally enters the capacitor 23 (see the “ef” line in the diagram of FIG. 2).

In addition, water vapor exiting from the DAC 9 of the steam turbine before its subsequent supply to the low pressure cylinder 10 of the steam turbine can be directed to the heated side (or cavity) of an additional organic superheater (not shown in the diagram), in which water vapor is heated at the pressure exiting CSD 9 of the exhaust steam to a temperature conjugate in magnitude to this pressure. Thus, as a result, the aforementioned economical two-time intermediate superheating of the steam sent to the steam turbine of the power plant can be provided with the aforementioned high-parameter known in steam-turbine power system of high parameters.

The water condensate formed in the condenser 23 is taken from there by a condensate pump 24 and then sent to the heated sides of the surface low pressure regenerative heaters (PND) 25, 26, from where the feed water enters the deaerator 29. In this case, the feed water is heated in the PND 25, 26 by CSD 9 turbines generate electricity by partial steam extraction, the condensate of which, under the influence of a differential pressure, enters the water cavity of the condenser 23. In addition, steam extraction is used to obtain heat energy economically from the DAC 9, the heating water in the network heat exchangers 32, 33 is similarly heated, through which the network pump 34 pumps water. From the feed tank of the deaerator 29, the feed water is drawn by the feed pump 30 and is compressed to a maximum pressure, which turns it into steam in the steam generators 4 Next, through the power plant power control, the feed valve 31 receives compressed feed water for further regenerative heating in the heated sides of the regenerative heaters pressure (LDPE) 27, 28 and then, having heated up to a predetermined nominal inlet temperature, it enters the heated sides of the steam generators 4 of the reactor installation.

For economical heat recovery of the gaseous products of combustion of superheaters 15 and 16, the outputs of these gases from the heating sides of these superheaters are fed to the heating side of the recovery boiler 19. As a result, the network water circulating through the pipe system 20 of the heated side of the recovery boiler 19 receives heat from the high-temperature combustion products and from using a network pump 21 and a shut-off and control device 22 transfers the received thermal energy to the consumer.

A positive quality of this embodiment of the electric power plant is that its power (exceeding the rated thermal power of the reactor) is regulated mainly by changing the consumption of fossil fuel supplied to superheaters 15, 16. This ensures a more stable temperature mode of operation of heat-stressed elements of RU equipment.

The proposed embodiment of the claimed invention has high reliability to ensure the continuity of production (with one or another capacity) of electric and thermal energy of the proposed EU in the following possible cases of operation:

During periods of cessation of the supply of organic fuel to the superheaters 15 and 16, the locking devices 6 and 14 are closed, and the locking device 13 is opened. Then, water vapor of relatively low parameters (65 ata and 290 ° C) coming out of 4 RU steam generators goes directly, bypassing compressor 7 and CVP 8, to the central cylinder 9, and then to the central cylinder 10 of the steam turbine. In this case, to reduce unnecessary mechanical losses, the coupler 12 disconnects the shafts of the steam turbine between the stopped CVP 8 with the compressor 7 and the common shaft of the DSC 9 and the low-pressure pulley 10 of the steam turbine (see line "a-f in the diagram of figure 2).

It is also possible to produce electric and thermal energy during periods of, for example, shutdown of a polytropic steam compressor and / or CVP 8. In this case, the locking devices 6 and 13 are closed and the locking device 14 is opened. Then the steam coming out of the 4 EU steam generators with a pressure of 65 atm and a temperature of 290 ° C can warm up in the superheater 15 to a conjugate (at that pressure of 65 ata) temperature of 450 ° C and then proceed to perform more economical operation in the central cylinder 9 and the low pressure cylinder 10 of the steam turbine (see line "ahf" in the diagram of figure 2). At the same time, as mentioned above, to reduce unnecessary mechanical losses, it is necessary that the coupling 12 disconnect the shaft connecting the stopped CVP 8 and the rotating DSM 9.

A quantitative assessment of the above work of option 1 of the proposed power plant with respect to, for example, the improvement of VVER-1000 and BN-800 atomic steam turbine power plants

1. Comparison indicators of the proposed version of the EU performance compared to VVER-1000 NPP.

1.1 Initial data of VVER-1000 NPP.

Nyap = 3000 MW (heat); Nel = 1068 MW el; Eph. Net efficiency = 35.6%.

Steam production D = 1633.3 kg / s; steam parameters - 70 ata / 285 ° C.

The cost of an installed kilowatt of generated electricity is $ 1,000 / kWel.

1.2 According to the proposed method of operation, the initial water vapor of the steam generators of nuclear power plants is compressed by a polytropic compressor to 130 at and 345 ° C. Taking into account the polytropic index n = 1.2 (see, for example, the book “Pumps, Compressors and Fans”, Z.S.Shlipchenko, Publishing House “Technika”, Kiev-1976, pp. 315-318) and fur. The compressor efficiency is 0.9, the electric power of a multi-stage polytropic compressor 7 will be 221 MW (e), and the final temperature of steam compression will be 345 ° С.

The following are known about the polytropic steam compressors required to create the proposed combined NPPs and APPPs. The journal Chemical and Oil and Gas Engineering, No. 8, 1999, on pages 33-34, lists compressors that do not even compress water vapor, but pairs of toxic and chemically active liquids such as methanol, nitric and hydrochloric acid (manufacturer of these compressors is the Polish company Turbo-Lodz). In the journal Chemical and Oil and Gas Engineering, No. 11, 1998, pages 4-15 show more than 20 large Russian enterprises designing and manufacturing a wide variety of powerful compressors for chemical oil and gas and refrigeration industry facts.

To ensure the operation of the improved VVER-1000 NPP with a serial domestic steam turbine operating at elevated conjugate initial steam parameters of 130 ata / 540 ° C / 540 ° C, the compressed steam is first heated with organic fuel in the first superheater 16 from 345 ° C to 540 ° C (the thermal power of the superheater will be 1100 MW t.) and then we operate in the CVP 8 of the steam turbine. Then, in the second superheater 15, we work out the 8 steam spent in the CVP at a pressure of ~ 25 atm from a temperature of 330 ° C to 540 ° C (the capacity of the superheater 16 will be 780 MW t.) And then we send it to the central cylinder 9 and the central cylinder 10 of the steam turbine. The total thermal power of the electric power station will be Nc = 3000 + 1100 + 780 = 4880 MW t. As a result, taking into account the electric efficiency of the technical and vocational schools equal to 42.0%, the output electric power of the technical and vocational schools will be Nvel = 4880 · 0.42 = 2050 MW el.

Taking into account the deduction of the electric costs of the steam turbine for the rotation of the compressor 7 (221 MW el), the useful electric power of the generator 11 of the improved nuclear power plant will be Npol = 2050-221 = 1829 MW el.

As a result, the effective electric net efficiency of the proposed nuclear power plant will be KPnetto = 1829/4880 = 37.5%, which is 5.3% (relative) higher than the efficiency of the initial VVER-1000 NPP.

Moreover, the additional electric power of the proposed power plant will be Ndop = 1829-1068 = 761 MW el, which will be 761/1068 = 0.712 = 71.2% of the rated power of VVER-1000 NPPs.

Thus, the useful electric power of the proposed power plant is 1829/1068 = 1.71 times the rated electric power of the VVER-1000 NPP.

1.3 Due to the achieved increase in electric efficiency of electric power plants from 35.6% to 37.5%, the relative savings of all (nuclear and organic) equivalent (in MJ / MW e) fuel of the proposed electric power will be 1-35.6 / 37.5 = 0.051 = 5.1% compared to the total fuel consumption of VVER-1000 NPP.

The annual consumption of additional organic fuel of the proposed EU at KIUM = 0.925 will be:

A) for natural gas - 1.64 billion m ³ per year;

B) for fuel oil - 1 377 917 tons of fuel oil per year.

If instead of the VVER-1000 serial water-water nuclear reactor, to produce the same amount of saturated water vapor (1633.3 kg / s) with a pressure of 70 ata, a traditional steam boiler operating on organic gaseous or liquid fuel is used, then the saving is more expensive (in equivalent energy) than nuclear, fossil fuels in this case will be 2.62 billion m ³ per year of natural gas or 2 198 804 tons of fuel oil per year, that is, 1.6 times more than the cost of similar additional fuel offered by bunny the present invention.

1.4 The total capital expenditures for the construction of the VVER-1000 NPP will amount to 1.07 billion US dollars.

However, according to the claimed invention, the electric power of the proposed nuclear power plant, including the same reactor installation, is increased by 761 MW (e). According to the article "Specific Capital Costs for the Construction of Thermal Power Plants Abroad" of the journal Teploenergetika, 1997, No. 2, pp. 77-79, the specific capital investments for the creation of modern thermal power plants amount to 1150-1470 dollars / kW el (2020) average). Therefore, the capital costs for the well-known construction of an alternative additional organic TPP with a capacity of 761 MW e will be:

Ctes = 7610001310 = $ 0.997 billion.

Therefore, the total capex for the creation of VVER-1000 NPPs and additional organic TPPs with a capacity of 761 MW el. will comprise:

Ks = 1.07 + 0.997 = 2.067 billion US dollars, and unit capital expenditures Kuds = 2.067 billion dollars / 1829 000 = 1130 dollars / kW el., Which is noticeable, i.e. 13% will surpass that of VVER-1000 nuclear power plants, which have a lower capacity of 1,068 MW el.

1.5 At the same time, the essence of the proposed technical solution is not in the well-known construction near the NPPs (for example, VVER-1000 NPPs) of an additional organic TPP, for example, with a capacity of 761 MW el., But only in the improvement of only the steam turbine unit of the existing (or already designed NPP ), consisting in the following:

- replacement or modernization of the steam turbine of the nuclear power plant to ensure its operation on the more economical paired parameters of the steam, widely tested in the power system;

- introduction to the steam-turbine part of the installation of a multi-stage (for example, 3) polytropic steam compressor, as well as at least one organic superheater and a waste heat boiler (exhaust products of fossil fuels).

Given the data in table. 5 of the above article of the journal "Heat and Power Engineering", the share of the above capital costs for additional equipment will be no more than 20-25% of the total capex for the construction of the VVER-1000 NPP, i.e.

Kdop = (0.20-0.25) · 1.07 = (0.214-0.267) billion dollars = (214-267) million US dollars.

Then the total capex for the creation of this 1st embodiment of a combined nuclear power plant (KNPP) with a capacity of 1829 MW (e) will be

Kkaes = 1.07 + (0.214-0.267) = (1.284-1.337) billion, US dollars,

And the specific capital costs for the construction of the KNPP will be equal to Kudkaes = (1.284-1.337) billion, dollars / 1,829,000 kW = (702-731) dollars / kW (e), which is significant, i.e. 27-30% less than the specific capex for the construction of existing VVER-1000 nuclear power plants.

Thus, in monetary terms, the savings in capital costs for the creation of one given 1-st version of the KNPP with an electric capacity of 1829 MW will be compared with the well-known construction of an additional organic TPP with a capacity of 761 MW of electric power. the following notable amount:

EECA = 2.067- (1.284-1.337) = (0.73-0.783) billion US dollars = (730-783) million US dollars.

Together, the above economic indicators provide a significant reduction in the cost of electricity produced by this embodiment of the proposed power plants.

Note: When the polytropic steam compressor 7 is rotated by an additional gas turbine unit 37, which, in accordance with claim 7, works using a heat exchanger-recuperator 42 (see option 2 of the proposed EA in Fig. 3) with a maximum efficiency of this gas turbine equal to 44 %, there will be the following improvements in the performance of the proposed power plant in comparison with the first option for improving the VVER-1000 NPP:

Its useful electric power will increase from 1829 MW el. to 1829 + 221 = 2050 MW (e), where 221 MW e is the power of compressor 7, now rotated by GTU 37, and not the steam turbine of the nuclear power plant. In connection with the foregoing, the effective electric efficiency (net) will increase compared with Option 1 of the proposed power plant from 37.5% to 38.1%, that is, 1.6% (rel.). At the same time, other technical, economic and operational indicators are improved accordingly (see option 2 of the proposed ES implementation below).

2. Comparison indicators of the proposed option 1 of the EU performance compared to the BN-800 nuclear power plant (see figure 3, 2).

2.1 Initial data of the BN-800 NPP.

Nyap = 2100 MW t .; Nel = 800 MW e; Ef. Efficiency = 38%.

Steam production D = 876 kg / s; GHG output initial steam parameters 140 ata and 490 ° С

2.2 According to the proposed method of operation, to reduce the energy consumption for compressing the vapor with a polytropic compressor 7, the feed water is precompressed with a feed pump (e.g. 31) to a maximum pressure (e.g. up to 220 atm), which ensures the conversion of water into steam in BN-800 steam generators.

Next, the steam leaving the steam generators with a pressure of 220 atm and a temperature of 490 ° C is compressed in the compressor 7 to an increased conjugate pressure of 290 atm.

As a result, the electric power of the compressor 7 will be a relatively small value of 75 MW el., And the final temperature of the vapor compression will be 525 ° C.

Further, to ensure the operation of the most famous steam turbine, the most economical in the power system, with coupled initial steam parameters of 290 at / 580 ° C / 580 ° C / 580/580 ° C, three organic steam preheaters with a total thermal capacity of 800 MW t are carried out.

As a result, the total thermal power of this example of an embodiment of a power plant will be Nsum = 2100 + 800 = 2900 MW heat.

Taking into account the fact that the actual net efficiency of a power unit with the above-mentioned steam turbine is the highest for modern steam turbines, 47%, the electric power of the technical training colleges of the proposed power plant will be Nel = 2900 · 0.47 = 1363 MW (e).

Excluding the electric costs required by the steam turbine to operate compressor 7 (75 MW el), the useful output electric power of this embodiment of the proposed power plant will be Nelp = 1363-75 = 1288 MW (el).

As a result, the effective electrical net efficiency of the proposed power plant example will be 1288/2900 = 44.4%, which is 16.9% (relative) higher than the sufficiently high effective efficiency of the BN-800 NPP. At the same time, for example, the relative savings of the total (nuclear and organic) equivalent (in MJ / MW e) will be the following noticeable value Et = 1-38.0 / 44.4 = 14.4%.

Moreover, the additional electric power of the proposed power plant will be Ndop = 1288-800 = 488 MW el., Which will be 488/800 = 0.61 = 61% of the nominal electric power of the BN-800 NPP.

Thus, the useful electric power of the proposed power plant is 1288/800 = 1.61 times the nominal value of the electric power of the BN-800 nuclear power plant at the same nominal steam capacity.

2.3 The annual consumption of additional organic fuel of the proposed EU at KIUM = 0.925 will be:

A) for natural gas - 0.7 billion m ³ per year;

B) for fuel oil 583 348 tons of fuel oil per year.

If instead of the serial fast sodium nuclear reactor BN-800 for the production of the same amount of water superheated steam (876 kg / s) with a pressure of 140 atm and a temperature of 490 ° C, a traditional steam boiler operating on organic gaseous or liquid fuel is used, then saving more expensive (in equivalent energy terms) than nuclear, fossil fuels in this case will be 1.84 billion m ³ per year of natural gas or 1,531,288 tons of fuel oil per year, that is, 2.65 times the cost of similar additional fuels a, proposed by the claimed invention.

2.4 According to our data, the specific capital investment for the construction of a BN-800 nuclear power plant is $ 1,350 / kW el, which in principle corresponds to the unit cost of advanced thermal power plants (TPPs) in the United States of $ 1,350-1600 / kW el (see Heat Power Engineering, 1997). , 32, p. 76-80).

According to the same magazine, the specific investment for the construction of modern American organic thermal power plants by 2020 will amount to 1150-1470 dollars / kW el (on average - 1310 dollars / kW el).

The maximum additional electric power of this example of the 2nd embodiment of the proposed EA is Ndop = 1288-800 = 488 MW el.

Consequently, the capital costs for the creation of an alternative organic BES-800 additional thermal power station with a capacity of 488 MW el. will make Ktes = 1310 · 488000 = 640 million dollars.

Therefore, the total capital expenditures for the construction of the BN-800 nuclear power plant and additional organic TPP with a capacity of 488 MW el. will be Ksum = 1350.800000 + 640000000 = 1.72 billion US dollars, and the specific capital costs will be equal

Kood = 1.72 billion dollars / 1288 000 kW = 1335 dollars / kW el.

2.5 At the same time, the essence of the proposed technical solution is not in the well-known construction near the NPP (for example, BN-800) of an additional organic TPP, for example, with a capacity of 488 MW el., But only in the improvement of only the steam turbine compartment of the NPP, which consists in the following:

Replacement or modernization of a steam turbine to ensure its operation on more economical, coupled initial steam parameters tested in the power system;

The introduction of a multi-stage polytropic compressor into the steam-turbine part of the electric control unit, as well as, for example, three organic superheaters and an exhaust gas boiler (combustion products of fossil fuels). Given the data in table. 5 of the above article of the journal "Heat Power Engineering" the share of the above capital costs for additional equipment will be more than 20-25% of the total capex for the construction of the BN-800 nuclear power plant, i.e. Kdop = (0.20-0.25) · 1350 · 800000 = (216-270) million US dollars.

Then the total cost of creating this embodiment of the proposed power plant with a capacity of 1288 MW e will be:

Kkaes = (1.20-1.25) · 1350 · 800000 = (1.3-1.35) billion US dollars, and the specific capital costs will be

Kudkaes = (1.3-1.35) billion dollars / 1288000 kW = (1009-1048) dollars / kW el, which will average 76% of the specific capital costs for the construction of the BN-800 NPP or 79% of the specific capital costs for the construction of modern American organic thermal power plants.

It follows that, in monetary terms, the savings in capital costs for the creation of this embodiment of the proposed power plant with a total capacity of 1288 MW el will be the following amount compared to the well-known construction of an additional organic TPP with a capacity of 488 MW el

Ekaes = Ks-Kkaes = 1.72- (1.3-1.35) = (0.370-0.420) billion US dollars = (370-420) million US dollars.

OPTION 2

This embodiment of the proposed atomic steam turbine power plant (see figure 3, 2) is preferable for cogeneration plants providing a wide range of consumers of electric and thermal energy.

As already indicated, in order to save the work of compressing a steam compressor, the fuel of a nuclear reactor 3, for example, a water-water type VVER-1000, is used in this EA primarily for energy-intensive (1517 kJ / kg at 284 ° C 65 ata) steam generation ( that is, the conversion of water into steam) of the working fluid of the steam-turbine part of the power plant with the maximum pressure and temperature of the steam leaving the steam generators 4 (or from a single-circuit water-water reactor) of the reactor installation (see, for example, point “a” on2 iagramme). At the same time, to rotate the polytropic multi-stage compressor 7, a gas turbine unit (GTU) 37 is launched, for which a polytropic steam compressor 7, as well as a gas turbine compressor 40 and a gas turbine 47, are rotated by an electric generator 38 operating during this period with a starting electric motor. power plants. In this case, the compressor 40 of the gas turbine 37 starts to suck up the combustion oxidizer - atmospheric air and feed it through the open shut-off device 46 into the combustion chamber 44, where simultaneously through the shut-off-regulating device 45 from the source of fossil fuels, gaseous or liquid fossil fuel starts to be supplied to the combustion chamber 44, which lights up.

As a result, the temperature of the compressed gaseous working fluid of the gas turbine 37 increases significantly in the combustion chamber 44 to a temperature of 1250 ° C and this working fluid is fed to the gas turbine 47 of the gas turbine 37 and the generator 38 goes into normal power generation mode minus the mechanical work, spent on the rotation of the polytropic steam compressor 7. When operating a nuclear reactor 3, the shut-off device 6 is open, and the shut-off devices 13 and 14 are closed. As a result, under the action of the compressor 7 cooled by the feed water in the heat exchangers 35, 36, water vapor exiting the steam generators 4, for example, with a pressure of 65 atm and a temperature of 290 ° C is compressed polytropically to the required high pressure, for example, to 240 ata (see line " a-b "in the diagram of figure 2).

Next, the compressed water vapor is directed to the heated side of the first superheater 16, where, due to the heat of combustion of a gaseous or liquid organic fuel mixed with atmospheric air, it is heated to a temperature corresponding to higher and therefore economical conjugate initial parameters (for example, to 540 ° C at 240 at , see line "b-c" in the diagram of figure 2). From the heated side of the superheater 16, high-temperature compressed water vapor is supplied to the high pressure cylinder (CVP) 8 of the steam turbine, where as a result of the loss of part of its internal energy it expands (for example, to 40 ata) and cools, for example, to 330 ° C ( see the line "cd" in the diagram of figure 2).

After the exhaust steam exits from CVP 8, this water vapor is supplied for intermediate overheating to the heated side of the second superheater 15, in which, due to the heat of combustion of gaseous or liquid organic fuel, it is heated at a pressure of 40 atm again to a temperature of 540 ° С conjugated to this intermediate pressure (cm line "de" in the diagram of figure 2).

The water condensate formed in the condenser 23 is taken from there by a condensate pump 24 and then sent to the heated sides of the surface regenerative low-pressure feed water heaters (PND) 25, 26, from where the heated feed water enters the deaerator 29. In this case, the feed water is heated in the PND 25, 26 partial heat of steam that has already produced electricity in the central turbine generator 9 of the turbine, the condensate of which, under the influence of a differential pressure, enters the water cavity of the condenser 23.

In addition, in order to obtain heat energy economically, the steam withdrawals from the DSP 9 similarly heat the heating water network in the network heat exchangers 32 and 33, through which the water pump 34 pumps water through the heated sides. From the deaerator feed tank 29, the feed water is drawn in by the feed pump 30 and is compressed to the maximum pressure that ensures its conversion into steam in steam generators 4. Further, through the power control unit of the power plant, the supply valve 31 can pressurized water in the heating season Xia in steam generators 4 closed by the locking device 52 to the bypass conduit 53 through the open shut-off device 54 and through the heated side of the economizer preheater 55, to the heating side of which is supplied for combustion through the shut-off control device 56 the gaseous or liquid organic fuel. At the same time, the shut-off devices 52 and 57 are closed and therefore, through the open shut-off devices 58 and 59 by the network pump 60, heat supply water is directed to the heated sides of the LDPE 27 and 28, which supplies the steam of the steam turbine with the heat of the steam generated in the DSS 9 and provides consumers with heat. Due to such combined, rather than separate production of electric and thermal energy, the specific saving of equivalent fuel will amount to 35-40 kg / MW · h of additional heat energy for heat supply.

In the non-heating season of operation of the cogeneration plant, the shut-off devices 54, 56, 58 and 59 are closed, and the shut-off devices 52 and 57 are opened, as a result of which feed water is sent to the steam generators 4 of the power plants through the steam-heated sides of the LDPE 27 and 28 according to the standard scheme with the economizer heater 55 turned off .

For economical heat recovery of gaseous superheaters 15, 16, as well as an economizer heater 55, the outflows of these gases from the heating sides of the superheaters 15, 16 and heater 55 are directed to the heating side of the recovery boiler 19. As a result, the network circulating through the pipe system 20 of the heated side of the recovery boiler is water takes in the heat of high-temperature combustion products and, with the help of a pump 21 and a shut-off and control device 22, transfers the received heat energy to the consumer.

In addition, the heat exchanger-recuperator 42 GTU 37 economically provides during the heating season a power plant with a noticeable amount of additional thermal energy as follows. During the operation of the EA in the mode with the maximum release of thermal energy during the heating season or during, for example, disconnection of the GTU shaft 37 from the shaft of the steam compressor 7 by the coupling sleeve 39 when the reactor is stopped (for example, when the overload is overloaded), the working fluid compressed by the compressor 40 GTU is sent with closed shut-off devices 41 and 43 through an open shut-off device 46 to the GTU combustion chamber 44, the power of which is increased correspondingly to the expanded temperature range (enthalpies) of the heated GTU 37 working fluid. thoron-recuperator heat exchanger 42 is connected through open shut-off devices 48 and 49 and pump 50 to the heat from exhaust gases selection consumer.

During operation of the installation in the mode with minimal heat energy to the consumer or during disconnection of the GTU shaft 37 from the steam compressor shaft 7 by the coupling sleeve 7 of the GTU 37 working body compressed by compressor 40 with closed shut-off devices 46, 48, 49 and open shut-off devices 41 and 43 pass as a heated medium through the heating side of the heat exchanger-recuperator 42, and the heat capacity of the combustion chamber 44 installed behind the compressor 40 is reduced in accordance with the reduced temperature range th working fluid GTU 37.

As a result of the above heat recovery in the GTU cycle, the electric efficiency of the gas turbine 37 and with it the electric efficiency of the entire power plant will increase accordingly during this period of time.

A positive feature of this version of the EA (as well as the first version) is that the main (over 100% heat. Reactor power) electric power of the power plant is regulated not by changing the reactor power, but mainly by changing the flow rate of gaseous or liquid organic fuel supplied to the superheaters 15, 16, the heater 55 and the combustion chamber 44 of the gas turbine 37.

The proposed second embodiment of the claimed invention is highly reliable from the point of view of ensuring the continuity of production to one degree or another of the electric and thermal energy of the proposed power plant in the following possible cases of operation of electric power plants:

During periods of cessation of the supply of organic fuel to the superheaters 15, 16, the locking devices 6 and 14 are closed, and the locking device 13 is opened. Then, water vapor of relatively low parameters (for example, 65 ata and 290 ° C) coming out of the steam generators 4 of the reactor unit 1 directly enters, bypassing the compressor 7 and CVP 8, to the central cylinder 9 and then to the central cylinder 10 of the steam turbine. In this case, to reduce unnecessary mechanical losses, the clutch 12 separates the shafts of the stopped CVP 8 and the central cylinder 9 and the central cylinder 10, which rotate the generator 11 (see line "a-f" in the diagram of figure 2).

It is also possible to produce a slightly larger amount of electric and thermal energy during periods, for example, shutdown of a polytropic steam compressor 7 and / or CVP 8. In this case, the shut-off devices 6 and 13 are closed and the shut-off device 14 is opened. Then 4 pairs leaving the steam generators with a pressure of 65 atm and a temperature of 290 ° C can be heated in a superheater 15 to a temperature of 450 ° C conjugated to a pressure of 65 ata and then act to perform more economical operation in the central cylinder 9 of the central pressure cylinder 10 of the steam turbine (see line, “ahf” in the diagram of FIG. 2). At the same time, as in the 1st version of the EU version, in order to reduce unnecessary mechanical losses, it is necessary that the coupling 12 disconnect the shaft of the standing CVP 8 from the shaft of the DSM 9, which rotates the electric generator 11 together with the central pressure cylinder 10.

This embodiment of the proposed EA provides the possibility of producing a noticeable amount of electrical and thermal energy even during periods of shutdown of a nuclear reactor 3 (for example, during its overload) and / or during a scheduled or other shutdown of a steam turbine of a power plant, as well as, for example, during emergency blackout circulation pumps of the 1st circuit of the switchgear.

The indicated possibility of generating electric and thermal energy is provided due to the above-mentioned work of the gas turbine 37, which rotates the additional electric generator 38 and generates heat through the heat exchanger-recuperator 42. In this case, the coupling sleeve 39 disconnected the shaft of the standing polytropic compressor 7 from the shaft of the working gas turbine 37.

Quantitative assessment of the above work option 2 execution of the proposed power plant

As a result of the design studies carried out at the first stage, three types of block reactor units were created on the basis of the mastered domestic technology of ship block reactors. Namely:

Three standard sizes of reactor units with a thermal power of 310, 460 and 735 MW heat, providing steam with high conjugate initial parameters to five different serial steam turbine plants: T-180 / 210-12.8; K-210-12.8-3 (6); K-310-23.5-3; T-250 / 300-23; K-500-17.7 (see, for example, the book "Steam Turbines", A.V. Scheglyaev, M., Energoatomizdat, 1993, book 1, pp. 74-98). Moreover, during the heating season, the production of electric and thermal energy is ensured in a range of capacities wide enough for the customer from 190 to 534 MW el. and from 180 to 500 (585) Gcal / h.

For comparison with the aforementioned APEC options, the table below shows the technical and economic indicators of the design of a traditional atomic heat and power plant (ATEC) operating only with a water-cooled dual-loop nuclear reactor R-800 with a thermal capacity of 800 MW.

The smaller transverse dimensions of the reactor units of the proposed combined ATEC IV compared with the ATEC R-800 reactor make it possible to carry out the factory (and not installation, during the construction of the ATEC) welding of the main pipe-in-tube nozzles of the reactor units (with an outer diameter of 640-960 mm) and general heat treatment in the factory furnace, after which the assembled reactor blocks of the hulls are transported to the ATEC construction site by surface and road transport. The indicated advantage (in addition to the steel safety case of the switchgear, which is especially important for the cogeneration plant located in the immediate vicinity of large residential areas) will ensure the equivalence of the welds of the main nozzles to the rest of the welded joints of the reactor, steam generator, etc., which will exclude the consideration of the hypothetical gap of the main branch pipes RU full section. At the same time, the positive feature of the proposed RU housing blocks is that the peripheral double housing blocks of the PG-GTsN ATEC I-V are unified. We also note that basically the power regulation of the proposed nuclear power plants in excess of the rated power of their reactors is carried out by the corresponding changes in the energy consumption of fossil fuels only in the steam part of the thermodynamic cycle of the operation of the PMT EI.

The absence or minimization of power and temperature transitions of reactors proposed by the ATEC, as well as the use of compact proven design and technological solutions (serial MCPs based on shipboard 360SP ЩК-650Б-3, as well as serial PTUs and gas turbines), up to using relatively small (diameter 7.0-8.5 m) of the steel safety case should significantly reduce the likelihood and reduce the scale of accidents and, therefore, significantly increase the nuclear and radiation safety of the nuclear power station during operation. The domestic serial gas turbines used for the proposed combined nuclear power plants are presented, for example, in the journal "Heat Power Engineering", 1992, No. 9, pp. 2-6.

So, the main technical and economic indicators of the five options offered by the 2nd embodiment of combined ATECs I-V in comparison with the traditional dual-circuit water-water ATEC R-800 are given in the table below.

From the above data, the following main conclusions can be drawn:

1. According to option 1, the proposed power plants are used mainly for power plants.

1.1 Compared to traditional water-cooled NPPs of the VVER-1000 type, the effective electric efficiency of the proposed power plants increases by 5.3-6.7% (relative), and the rated electric power of the electric power plants, including the same reactor unit with nominal steam capacity, increases by 1.70-1.92 times.

1.2 Compared to the well-known sodium BN-800 NPP, the effective electric efficiency of the proposed power plants increases by 16.9% (rel.), And the nominal electric power of a power plant, including the same reactor with a nominal steam capacity, increases by 1.61 times.

2. According to option 2, the proposed power plants are used mainly for combined heat and power plants

2.1 Compared with traditional nuclear power plants with water-cooled nuclear reactors, the electrical efficiency of the proposed combined nuclear power plants increases in the heating season from 25% to 27-31%, which practically corresponds to the electrical efficiency in the heating season of modern purely organic steam turbine thermal power plants operating at higher conjugate steam parameters (see, for example, the journal "Heat Power Engineering", No. 9, 1992, p. 4).

2.2 The proposed power plants provide a significant (2.6-fold) increase in the production of electric energy in comparison with traditional nuclear power plants, which include a water-water nuclear reactor of the same thermal capacity.

2.3 The saving in the heating season of all (nuclear and organic) equivalent (in MJ / kW el) fuel is from 6.7% to 17.8% compared with the traditional R-800 ATEC.

2.4 The specific amount of electricity in MW el. Produced by the proposed APEC in the heating season from one MW heat. RU exceeds the same indicator of traditional nuclear power plants with light-water nuclear reactors by 2.36-3.00 times.

2.5 The specific amount of thermal energy in Gcal / h produced by the proposed ATEC during the heating season from one MW of heat. RU exceeds the same indicator of a traditional nuclear power plant with light-water nuclear reactors by 1.1-2.6 times.

3. All proposed power plants have significantly lower specific capital costs for their construction (see paragraphs 1.5 and 2.5 of the description, as well as paragraph 15 of the table) compared to traditional nuclear power plants and nuclear power plants and, accordingly, lower costs for the production of electric and thermal energy.

The above production and economic indicators of the implementation of the proposed technical solution allow us to conclude that it is quite competitive in comparison with well-known analogues.

Claims (6)

1. A method of operating an atomic steam-turbine power plant, in which the water compressed by a feed pump is converted into a carrier of thermal energy — steam, which is subsequently heated in at least one superheater, to the heating side of which in the reactor installation due to the heat of nuclear fuel mainly gaseous or liquid fossil fuels are supplied for combustion, as well as an oxidizing agent in the form of, for example, atmospheric air, and then superheated steam of the associated direction parameters t for commissioning a steam turbine of the installation equipped with, among other things, surface regenerative heaters of feed water, which is obtained in the condenser of the steam turbine part (PTC) of the installation, to perform work in the rotary electric generator, characterized in that the steam coming from the steam generator of the reactor installation is compressed to a higher pressure in at least one, for example, multi-stage, compressor, mainly with intermediate cooling of its stages by the feed water of the installation. 2. The method according to claim 1, characterized in that the spent steam in the high pressure cylinder (CVP) of the steam turbine is heated in the heated side of at least one superheater, in the heating side of which mainly gaseous or liquid organic fuel is fed for combustion, and also an oxidizing agent in the form of atmospheric air, after which the secondarily superheated water vapor is sent further along the standard path of the cylinders of the steam turbine of the power plant. 3. The method according to claim 1, characterized in that the feed water is compressed by the feed pump to the maximum pressure before entering the steam generator, which, at nominal thermodynamic parameters of the heating coolant, provides water to steam in the heated sides of the steam generator of the installation, as a result of which, together with subsequent compression of the resulting steam by the compressor and its additional heating, in one or two intermediate steam superheater of the steam turbine get higher conjugate initial parameters steam, which provide more economical operation of the steam turbine unit and the power plant as a whole. 4. The method according to claim 1, characterized in that the water-vapor compression compressor is rotated by a steam turbine of a power plant or a second gas turbine power plant (GTU) rotating a second electric generator, the combustion chamber of which runs on organic fuel, and the exhaust gases of a gas turbine are directed to the heating side of the heat exchanger - a recuperator that provides the consumer with hot water or steam from the heated side of the heat exchanger-recuperator during the heating season. 5. The method according to claim 4, characterized in that during periods of shutdown (for example, during scheduled reloading of nuclear fuel) of the nuclear reactor and / or shutdown of the steam turbine part of the installation, electrical and, if necessary, thermal energy is produced due to the operation of the gas turbine power plant (GTU) ), the shaft of which is mainly disconnected from the shaft of the compressor for compressing water vapor. 6. Atomic steam turbine power plant, including a reactor plant that produces a carrier of thermal energy - water vapor (working medium of the PTC installation), and also a steam turbine plant including piping to the reactor plant for steam and feed water, including the heated side of the steam generator, the heated side, at least at least one steam superheater, the heating side of which is connected through shut-off and control devices to a source of gaseous or liquid organic fuel as well as, for example, through a gas blower with atmospheric air for burning fuel, a steam turbine driving an electric generator, a condenser, a condensate pump, a deaerator, a feed pump, and also, mainly, surface regenerative feed water heaters, characterized in that the output steam from the heated side of the steam generator of the switchgear is connected through shut-off devices simultaneously with the steam inlet into the multi-stage polytropic, cooled mainly feed water compressor driven the action of either a steam turbine or a gas turbine power plant (GTU), the combustion chamber of which is made with the possibility of heating with gaseous or liquid organic fuel, and is also connected to the steam inlet to the medium pressure working cylinder (CSD) of the steam turbine and to the steam inlet to the superheater, which in turn, it is connected to the steam turbine central cylinder, while the output of compressed water vapor from the polytropic compressor is connected to the steam inlet to the high pressure cylinder (CVP) of the steam turbine through the heated side of the steam a superheater, and the exhaust gas outlet from the gas turbine of the gas turbine unit driving the steam compressor and the second generator of the installation is connected to the heating side of the heat exchanger-recuperator, the heated side of which is simultaneously connected through shut-off devices to the outlet of compressed air from the gas turbine compressor, with the heated air inlet GTU combustion chamber, as well as with the circulation circuit of the consumer of thermal energy.

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