Single-Loop Nuclear Power Plant with Pressurized Coolant
20210098141 ยท 2021-04-01
Inventors
- Sergey Viktorovich KOROVKIN (Dolgoprudniy Moscovskaya obl., RU)
- Evgeniya Viktorovna TUTUNINA (Moscow, RU)
Cpc classification
Y02E30/30
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
Y02E30/00
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
International classification
Abstract
A single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected to the throttling device and to a condenser connected to the throttling device, which device is a throttling steam generator vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by horizontal sealed partitions. The high pressure zone is connected to the the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the the horizontal sealed partitions and the high pressure zone. The single-loop nuclear power plant is provided with an electric motor to rotate the impeller.
Claims
1. A single-loop nuclear power plant with a heat-carrier under pressure, including a power unit and a throttling device which are connected by means of output and feed pipelines, a steam turbine, which is connected by means of pipes to the throttling device and to a condenser, which is also connected to the throttling device, characterized in that it also includes an electric drive which is connected to a working wheel and configured to rotate it, and a throttling device which is configured in the form of a throttle steam generator which is vertically separated into a zone of a steam space, into a zone of high pressure and into a zone of reduced pressure, which zones are separated by horizontal hermetic partitions, the zone of the steam space being located higher than the zone of high pressure, which in turn is located higher than the zone of reduced pressure, the zone of high pressure being connected to the inlet of the output pipeline and being connected to the zone of reduced pressure by means of throttling nozzles, which are arranged in the partition between said zones at its periphery under an angle towards the vertical, the zone of reduced pressure being connected to the steam space zone by means of a vertical pipeline which passes through the centers of the horizontal hermetic partitions and the zone of high pressure.
2. Single-loop nuclear power plant with a heat carrier under pressure according to claim 1, characterized in that the electric drive is connected to the steam turbine.
3. Single-loop nuclear power plant with a heat carrier under pressure according to claim 1, characterized in that it is further provided with a reserve diesel generator which is connected to the electric drive and configured to feed electricity to the electric drive.
4. Single-loop nuclear power plant with a heat carrier under pressure according to claim 1, characterized in that it is further provided with a steam regulating valve which is arranged in the pipeline which connects the throttle steam generator and the steam turbine and which is able to regulate and close the stream of steam.
5. Single-loop nuclear power plant with a heat carrier under pressure according to claim 1, characterized in that it further comprises a feed pump which is arranged in the pipeline which connects the condenser and the throttle steam generator.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
[0016] In the figures is shown a schematic representation of the construction of a single-loop nuclear power station in a preferred embodiment, comprising a power unit made in the form of a nuclear reactor 1 with an active zone 2 connected by means of a discharge pipe 3 and a supply line 15 with a throttle device made in the form of a throttle steam generator 4 with a working wheel 13, divided into a high-pressure zone 5, a zone of reduced pressure 6 and a zone of a steam space 7, which are separated by hermetic horizontal partitions, at the periphery of the horizontal hermetic partition dividing the high-pressure zone 5 and the low-pressure zone 6, there are provided at an inclination to the vertical throttle nozzles 8, the high-pressure zone 8 being connected to the inlet of the discharge pipe 3, the low-pressure zone 6 being connected to the zone of the steam space 7 by a vertical pipeline passing through the centers of the horizontal hermetically sealed partitions and the high-pressure zone. The single-loop atomic power plant is provided with an electric drive of the main circulation pump 14 capable of rotating the working wheel (impeller) 13, with a steam control valve 9 located in the pipe connecting the throttle steam generator 4 and a steam turbine 10 which in turn is connected by a pipeline with a condenser 11 connected in turn with a pipeline on which the feed pump 12 is mounted, with a throttle steam generator 4.
REALIZATION OF THE INVENTION
[0017] The single-loop atomic power station of the present invention preferably operates as follows.
[0018] The pressurized water is pumped through the active zone 2, which is in the housing of the nuclear reactor 1, which is heated and fed via the discharge line 3 of the reactor 1 to the throttle steam generator 4 consisting of the high-pressure zone 5, the zone of reduced pressure 5 and the zone of the steam volume 7. High-pressure zone 5 and reduced-pressure zone 6 are separated by a horizontal hermetic partition with throttle nozzles 8 installed in it and made for a reduction of the pressure and an acceleration of hot water flow. In the throttle nozzles 8, the pressure of the hot water drops below the saturation pressure, so that the hot water boils and the resulting two-phase stream is accelerated. The throttle nozzles 8 are inclined to the vertical in such a way that the two-phase flow is twisted around the axis of the throttle steam generator 4. Due to the centrifugal force, the water in the low-pressure zone 6 is thrown to the walls of the throttle valve steam generator 4, and steam is passed through vertical pipeline into steam space zone 7, from which it enters a steam turbine 10 through steam regulating valve 9, the rotor of which is connected to the rotor of electric generator. Spent steam used in steam turbine 10 is condensed in condenser 11 and the condensed water by a pump of feed water 12 is supplied to the throttle steam generator 4 to the working wheel of the circulation pump 13, which is driven by the electric drive 14 receiving electric power from the steam turbine 10. Further, the water flow consisting of the separated rotating water of the reduced pressure zone and the feed water by the working wheel 13 is fed through the supply branch pipe 15 tin the nuclear reactor again, whereby the pressure of the water is increased to the pressure in the reactor 1 due to the kinetic energy of the rotating water and the rotation of the working wheel. The conversion of the kinetic energy of the rotating water into the potential energy of pressure makes it possible to considerably reduce the consumption of electric power by the circulating pump for increasing the pressure of the water flow.
[0019] The electric dive 14 operates as follows: in normal operation, it receives electric power from the rotor of the electric generator which is connected to the rotor of the steam turbine, in the emergency mode it is possible to supply the electric motor 14 from the backup diesel generators of the NPS, when the NPS is started, the electric motor 14 can receive electric power from an industrial network, diesel generators, or any other external source. These possibilities, distinguishing the present invention from [2], provide an increase in the reliability and safety of operation of a single-loop nuclear power station with a heat transfer medium under pressure in all modes.
[0020] The steam control valve 9 may be used in the start-up mode of the NPS. For this, during start-up, the steam control valve 9 is closed to provide sufficient steam pressure, whereupon the opening of the steam control valve 9 causes the steam turbine 10 to be started.
[0021] The calculations show that at the water parameters at the outlet of the reactor and the parameters of the steam at the turbine inlet similar to those of the NPS with the reactor VVER-1000, the consumption of electric power to the drive of the impeller 13 will be no more than 3% of that produced by the steam turbine 10, which is similar to the power consumption of the main circulation pumps at the double-loop nuclear power station with the reactor VVER-1100.
[0022] The essence of the claimed invention is not limited to the above-described versions. Skilled persons of the relevant technical field can supplement it with additional embodiments.
INDUSTRIAL APPLICABILITY
[0023] The single-loop nuclear power station with a heat carrier under pressure provides high efficiency of the use of nuclear fuel, as well as reliability and safety of its operation in all modes and can be used in nuclear power engineering.