CN210118175U - Pressurized water reactor nuclear power unit two-loop thermodynamic system self-adaptation steam supply system - Google Patents
Pressurized water reactor nuclear power unit two-loop thermodynamic system self-adaptation steam supply system Download PDFInfo
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Abstract
The utility model discloses a two return circuits thermodynamic system self-adaptation steam supply system of pressurized water reactor nuclear power unit, this system can open at the unit and open and stop and the normal operating in-process, according to two return circuit heating power parameters, the heating vapour source of low pressure heater, oxygen-eliminating device and high pressure feed water heater is supplied with to the main steam bypass of self-adaptation ground input or excision, avoid the long-term hot stand-by state's of auxiliary boiler drawback, realize the step recycle of energy, reliability, stability and security are higher simultaneously, and the consumption is lower.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power, a pressurized water reactor nuclear power unit two return circuits thermodynamic system self-adaptation steam supply system is related to.
Background
Pressurized water reactors are currently in widespread use as a technically mature reactor model. The secondary loop thermodynamic system of the pressurized water reactor nuclear power unit comprises a steam generator, a steam turbine, a steam-water separation reheater, a condenser, a low-pressure heater, a deaerator, a high-pressure heater, a pump, a valve and a connecting pipeline. The general design scheme of the two-loop thermodynamic system is as follows: after condensed water in the condenser is heated by the low-pressure heater, the deaerator and the high-pressure heater in sequence, the water temperature of the secondary side inlet of the steam generator meets the unit operation requirement. When the unit normally operates with load, the steam sources of the low-pressure heater, the deaerator and the high-pressure heater come from the extraction steam of each stage of the steam turbine; the steam of the steam turbine shaft seal comes from auxiliary steam when the steam turbine runs at low load, and the steam turbine reaches a self-sealing state when the steam turbine runs at high load; the auxiliary steam is supplied by the main steam system. In the starting and stopping process of the unit, the heating steam source of the deaerator and the shaft seal steam come from auxiliary steam; auxiliary steam is supplied by an auxiliary boiler.
The above design has at least the following disadvantages:
a) in the start-stop stage of the unit, all stages of steam extraction of the steam turbine cannot be put into use, the water temperature of the secondary side inlet of the steam generator can be improved only by supplying steam to the deaerator through auxiliary steam, and the auxiliary boiler needs to operate for a long time and has the problems of high cost, poor heating effect and instability;
b) during the start-stop and low-load operation processes of the unit, a large amount of main steam is discharged to the condenser through the bypass system, the high-temperature and high-pressure main steam is directly condensed after being discharged into the condenser, and the energy of the main steam is not recycled in a gradient manner;
c) high-temperature main steam is discharged into the condenser, so that the temperature of condensed water is increased, the efficiency of the steam turbine is reduced, and the power consumption of the circulating cooling water pump is increased;
d) after the main steam enters the condenser and becomes condensed water, the part of the condensed water enters the deaerator, and the power consumption of a condensed water pump needs to be additionally increased;
e) when the unit normally operates, the auxiliary boiler needs to be in a hot standby state for a long time, so that a deaerator and a shaft seal steam source can be provided in the normal stop process of the unit, the long-term hot standby state is not beneficial to the safe and stable operation of the auxiliary boiler, and meanwhile, the energy consumption of the auxiliary boiler is increased;
f) when the steam turbine is in emergency shutdown under the operating condition of shutdown and non-shutdown, all the extracted steam of each stage is lost, the heating steam sources of the high-pressure heater, the low-pressure heater and the deaerator are instantaneously lost, the water supply temperature at the inlet of the evaporator is rapidly reduced, and a primary loop is extremely easy to be supercooled to cause non-shutdown accidents of the reactor.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to overcome above-mentioned prior art's shortcoming, a pressurized water reactor nuclear power unit two return circuits thermodynamic system self-adaptation steam supply system is provided, this system can open at the unit and open and stop and the normal operating in-process, according to two return circuits heating power parameter, self-adaptively drop into or amputate main steam bypass and supply with low pressure heater, oxygen-eliminating device and high pressure feed water heater's heating vapour source, avoid the drawback of the long-term hot stand-by state of auxiliary boiler, realize the step recycle of energy, reliability simultaneously, stability and security are higher, and the consumption is lower.
In order to achieve the above object, the self-adaptive steam supply system of two-loop thermodynamic system of a pressurized water reactor nuclear power unit comprises a steam generator, a high-medium pressure cylinder of a steam turbine, a low-pressure cylinder of a steam turbine, a generator set, a condenser, a low-pressure heater, a deaerator, a high-pressure heater, a shaft seal steam supply system, a steam-water separation reheater, a steam turbine steam inlet valve bank, a main steam supply valve bank, a main steam supply shaft seal system valve bank, a high-pressure cylinder one-section steam extraction valve bank, a main steam supply steam-water separation reheater valve bank, a steam-water separation reheater inlet valve bank and a steam-water separation reheater outlet valve bank, an auxiliary steam system, an auxiliary steam supply shaft seal system valve bank, an auxiliary steam supply deaerator valve bank, a main steam bypass valve bank, a low-pressure cylinder steam extraction valve bank, a main steam, The high-pressure cylinder extracts steam to supply the high-pressure heater valve bank and the main steam bypass supplies the high-pressure heater valve bank;
the secondary side outlet of the steam generator is divided into three paths, wherein the first path is communicated with the inlet of the steam inlet valve group of the steam turbine, the second path is communicated with the inlet of the main steam supply valve group, and the third path is communicated with one end of the main steam bypass;
the outlet of the steam turbine steam inlet valve group is communicated with the inlet of a high and medium pressure cylinder of the steam turbine, the low pressure cylinder of the steam turbine and the generator set are connected, the steam exhaust port of the high and medium pressure cylinder of the steam turbine is divided into two paths, wherein one path is communicated with the inlet of a steam-water separation reheater through a steam-water separation reheater inlet valve group, the other path is communicated with the inlet of a deaerator valve group through high pressure cylinder exhaust steam, the outlet of the steam-water separation reheater is communicated with the inlet of the low pressure cylinder of the steam turbine through a steam-water separation reheater outlet valve group, the steam exhaust port of the low pressure cylinder of the steam turbine is communicated with the inlet;
the outlet of the main steam supply valve bank is divided into two paths, one path is communicated with the secondary reheater inlet of the steam-water separation reheater through the main steam supply steam-water separation reheater valve bank, and the other path is communicated with the shaft seal steam supply system through the main steam supply shaft seal system valve bank; a section of steam extraction port of the high-pressure cylinder in the high-intermediate pressure cylinder of the steam turbine is communicated with a first-stage reheater inlet of a steam-water separator reheater through a section of steam extraction valve bank of the high-pressure cylinder;
the outlet of the auxiliary steam system is divided into two paths, one path is communicated with the inlet of the shaft seal steam supply system through an auxiliary steam supply shaft seal system valve group, the other path is communicated with the inlet of the deaerator through an auxiliary steam supply deaerator valve group, the steam outlet of the high and medium pressure steam turbine cylinder is communicated with the inlet of the high pressure steam cylinder steam exhaust deaerator valve group, the other end of the main steam bypass is communicated with the inlet of the main steam bypass high pressure heater valve group, the inlet of the main steam bypass deaerator valve group, the inlet of the main steam bypass low pressure heater valve group and the inlet of the main steam bypass valve group, the steam extraction port of the high and medium pressure steam turbine cylinder is communicated with the inlet of the high pressure steam cylinder high pressure heater valve group, and the steam extraction port of the low pressure steam turbine cylinder is communicated with the;
an outlet of the high-pressure cylinder steam extraction high-pressure heater valve group and an outlet of the main steam bypass high-pressure heater valve group are communicated with an inlet of the high-pressure heater through a pipeline;
an outlet of the main steam bypass deaerator valve bank and an outlet of the high-pressure cylinder exhaust deaerator valve bank are communicated with an inlet of a deaerator after being connected in parallel through a pipeline;
the outlet of the low-pressure cylinder steam extraction valve group and the outlet of the main steam bypass low-pressure heater valve group are communicated with the inlet of the low-pressure heater through a pipeline.
The outlet of the condenser is communicated with the inlet of the low-pressure heater through a condensate pump.
The high and medium pressure cylinders of the steam turbine, the low pressure cylinder of the steam turbine and the generator set are coaxially connected.
The outlet of the deaerator is communicated with the inlet of the high-pressure heater through a water feed pump.
The utility model discloses following beneficial effect has:
the utility model discloses a pressurized water reactor nuclear power unit two return circuits thermodynamic system self-adaptation steam supply system when concrete operation, in the unit start-up process, utilize main steam bypass to provide the heating steam source for low pressure feed water heater, deaerator and high pressure feed water heater to promote the feedwater temperature of steam generator secondary side entrance, make main steam parameter satisfy the rush requirement of steam turbine as soon as possible, shorten unit start-up time, in addition, supply the deaerator through main steam bypass and carry out thermal deoxidization, withdraw from the operation as early as possible after starting the boiler, solve and start the boiler and need long-time running problem, energy-conserving effect has; in the process of starting and stopping and normal operation of the unit, the main steam bypass is adaptively put into or cut off according to the steam pressure of each part to supply heating steam sources of the low-pressure heater, the deaerator and the high-pressure heater, the defect of long-term hot standby state of the auxiliary boiler is avoided, the gradient recycling of energy is realized, and the energy consumption of the system is reduced. In addition, in the unit stopping process, the heating steam source through the high-pressure heater, the low-pressure heater and the deaerator is timely input, the safe and stable operation of the steam generator is guaranteed, under the shutdown and non-stop operation working condition, the secondary side water supply of the steam generator is heated by the main steam bypass, the severe fluctuation of the water supply temperature of the inlet of the steam generator is avoided, the operation safety of the unit is improved, the unit restarting time is shortened, the dependence on auxiliary steam in the unit starting, stopping and operating processes is reduced, and the safe and stable operation of the pressurized water reactor nuclear power generating unit is facilitated.
Drawings
Fig. 1 is a schematic structural diagram of the present invention.
Wherein, 1 is a steam generator, 2 is a steam turbine steam inlet valve bank, 3 is a steam turbine high-medium pressure cylinder, 4 is a steam turbine low-pressure cylinder, 5 is a generator set, 6 is a condenser, 7 is a condensate pump, 8 is a low-pressure heater, 9 is a deaerator, 10 is a water feed pump, 11 is a high-pressure heater, 12 is a main steam supply valve bank, 13 is a main steam supply shaft seal system valve bank, 14 is a shaft seal steam supply system, 15 is an auxiliary steam supply shaft seal system valve bank, 16 is an auxiliary steam system, 17 is an auxiliary steam supply deaerator valve bank, 18 is a main steam bypass valve bank, 19 is a low-pressure cylinder steam extraction valve bank, 20 is a main steam bypass low-pressure heater valve bank, 21 is a main steam bypass deaerator valve bank, 22 is a high-pressure cylinder steam exhaust steam supply deaerator valve bank, 23 is a high-pressure cylinder steam extraction high-pressure valve bank heater, 24 is a main steam bypass high-pressure heater valve bank, 26 is a moisture separator reheater, 27 is a main steam supply moisture separator reheater valve bank, 28 is a moisture separator reheater inlet valve bank, and 29 is a moisture separator reheater outlet valve bank.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings:
referring to fig. 1, the self-adaptive steam supply system of the two-loop thermodynamic system of the pressurized water reactor nuclear power plant comprises a steam generator 1, a steam turbine high-medium pressure cylinder 3, a steam turbine low-pressure cylinder 4, a generator set 5, a condenser 6, a low-pressure heater 8, a deaerator 9, a high-pressure heater 11, a shaft seal steam supply system 14, a steam-water separation reheater 26, a steam turbine steam inlet valve bank 2, a main steam supply valve bank 12, a main steam supply shaft seal system valve bank 13, a high-pressure cylinder one-section steam extraction valve bank 25, a main steam supply steam-water separation reheater valve bank 27, a steam-water separation reheater inlet valve bank 28, a steam-water separation reheater outlet valve bank 29, an auxiliary steam system 16, an auxiliary steam supply shaft seal system valve bank 15, an auxiliary steam supply deaerator valve bank 17, a main steam bypass valve bank 18, a low-pressure cylinder steam extraction valve bank 19, a, A high-pressure cylinder exhaust steam supply deaerator valve bank 22, a high-pressure cylinder exhaust steam high-pressure heater valve bank 23 and a main steam bypass high-pressure heater valve bank 24;
the secondary side outlet of the steam generator 1 is divided into three paths, wherein the first path is communicated with the inlet of the steam inlet valve group 2 of the steam turbine, the second path is communicated with the inlet of the main steam supply valve group 12, and the third path is communicated with one end of a main steam bypass; the outlet of the steam turbine steam inlet valve group 2 is communicated with the inlet of the steam turbine high and medium pressure cylinder 3, the steam turbine low and medium pressure cylinder 4 and the generator set 5 are connected, the steam exhaust port of the steam turbine high and medium pressure cylinder 3 is divided into two paths, one path is communicated with the inlet of a steam-water separation reheater 26 through a steam-water separation reheater inlet valve group 28, the other path is communicated with the inlet of a deaerator valve group 22 through high pressure cylinder exhaust steam, the outlet of the steam-water separation reheater 26 is communicated with the inlet of the steam turbine low pressure cylinder 4 through a steam-water separation reheater outlet valve group 29, the steam exhaust port of the steam turbine low and medium pressure cylinder 4 is communicated with the inlet of a condenser 6, and the outlet of the condenser 6 is communicated with;
the outlet of the main steam supply valve bank 12 is divided into two paths, one path is communicated with the secondary reheater inlet of the steam-water separation reheater 26 through a main steam supply steam-water separation reheater valve bank 27, and the other path is communicated with the shaft seal steam supply system 14 through a main steam supply shaft seal system valve bank 13; a section of steam extraction port of the high-pressure cylinder and the middle-pressure cylinder of the steam turbine 3 is communicated with a first-stage reheater inlet of a steam-water separator reheater 26 through a section of steam extraction valve bank 25 of the high-pressure cylinder;
the outlet of the auxiliary steam system 16 is divided into two paths, one path is communicated with the inlet of the shaft seal steam supply system 14 through an auxiliary steam supply shaft seal system valve group 15, the other path is communicated with the inlet of a deaerator 9 through an auxiliary steam supply deaerator valve group 17, the steam outlet of the high and medium pressure turbine cylinder 3 is communicated with the inlet of a high pressure cylinder steam discharge deaerator valve group 22, the other end of the main steam bypass is communicated with the inlet of a main steam bypass high pressure heater valve group 24, the inlet of a main steam bypass deaerator valve group 21, the inlet of a main steam bypass low pressure heater valve group 20 and the inlet of a main steam bypass valve group 18, the steam outlet of the high and medium pressure turbine cylinder 3 is communicated with the inlet of a high pressure cylinder steam discharge high pressure heater valve group 23, and the steam outlet of the low pressure turbine cylinder 4 is communicated with the inlet of a low pressure cylinder;
the outlet of the high-pressure cylinder steam extraction high-pressure heater valve group 23 and the outlet of the main steam bypass high-pressure heater valve group 24 are communicated with the inlet of the high-pressure heater 11 through pipelines and pipes; an outlet of the main steam bypass deaerator valve bank 21 and an outlet of the high-pressure cylinder steam exhaust deaerator valve bank 22 are communicated with an inlet of the deaerator 9 through pipelines and pipes; the outlet of the low-pressure cylinder steam extraction valve group 19 and the outlet of the main steam bypass low-pressure heater valve group 20 are communicated with the inlet of the low-pressure heater 8 after being connected in parallel through a pipeline.
The outlet of the condenser 6 is communicated with the inlet of the low-pressure heater 8 through a condensate pump 7; the steam turbine high and medium pressure cylinder 3, the steam turbine low pressure cylinder 4 and the generator set 5 are coaxially connected; the outlet of the deaerator 9 is communicated with the inlet of the high-pressure heater 1 through a water feeding pump 10.
The utility model comprises two loops starting, two loops normally stopping and unit stopping without shutdown;
the specific process of the two-loop starting is as follows:
1a) in the starting process of the second loop, steam is supplied by the auxiliary steam system 16, the steam output by the auxiliary steam system 16 is divided into two paths, wherein one path of steam enters the deaerator 9 through the auxiliary steam deaerator valve set 17 to heat and feed water, and water in the deaerator 9 enters the steam generator 1 through the high-pressure heater 11; the other path of steam enters a shaft seal steam supply system 14 through an auxiliary steam shaft seal system valve group 15;
2a) with the increase of the reactor power, after steam is generated at the secondary side outlet of the steam generator 1, opening the main steam supply valve bank 12, gradually opening the main steam supply steam-water separation reheater valve bank 27, and performing pipe heating on a secondary reheater of the steam-water separation reheater 26; gradually opening a main steam supply shaft seal system valve group 13, adjusting the steam amount entering a shaft seal steam supply system 14 through the main steam supply shaft seal system valve group 13 until an auxiliary steam supply shaft seal system valve group 15 is closed, wherein at the moment, a main steam bypass valve group 18, a low-pressure cylinder steam extraction valve group 19, a main steam bypass low-pressure heater valve group 20, a main steam bypass deaerator valve group 21, a high-pressure cylinder steam exhaust deaerator valve group 22, a high-pressure cylinder steam extraction high-pressure heater valve group 23, a main steam bypass high-pressure heater valve group 24, a high-pressure cylinder one-section steam extraction valve group 25, a steam-water separator inlet valve group 28 and a steam-water separator reheater outlet valve group 29 are in a closed state;
3a) the reactor power is continuously increased, the main steam bypass valve bank 18 is gradually opened, when the pressure at the inlet of the main steam bypass valve bank 18 is higher than the pressure at the steam side of the low-pressure heater 8, a stop valve in the main steam bypass low-pressure heater valve bank 20 is opened, the amount of steam entering the low-pressure heater 8 is adjusted by the main steam bypass low-pressure heater valve bank 20, and the water temperature at the outlet of the low-pressure heater 8 is controlled;
4a) when the pressure at the inlet of the main steam bypass valve bank 18 is higher than the pressure of the deaerator 9, opening a stop valve in the main steam bypass deaerator valve bank 21, feeding the steam into the deaerator 9 through the main steam bypass deaerator valve bank 21, gradually reducing the steam supply of the auxiliary steam system 16 until the auxiliary steam deaerator valve bank 17 is completely closed, and completely cutting off the auxiliary steam;
5a) when the pressure at the inlet of the main steam bypass valve bank 18 is higher than the pressure at the steam side of the high-pressure heater 11, a stop valve in the main steam bypass high-pressure heater valve bank 24 is opened, and the amount of steam entering the high-pressure heater 11 is adjusted through the main steam bypass high-pressure heater valve bank 24 so as to control the water temperature at the outlet of the high-pressure heater 11;
6a) when steam parameters at the outlet of the steam generator 1 meet the requirement of the steam turbine on the running of the steam turbine, the steam turbine is run, and in the running process, the steam amount required by the running of the steam turbine and the load is adjusted through the main steam bypass valve bank 18; opening a steam-water separation reheater inlet valve set 28 and a steam-water separation reheater outlet valve set 29, and enabling exhaust steam of the steam turbine high-intermediate pressure cylinder 3 to enter the steam turbine low-pressure cylinder 4 after passing through a steam-water separation reheater 26; opening a stop valve in the high-pressure cylinder first-stage steam extraction valve bank 25, and adjusting the amount of steam entering a first-stage reheater of the steam-water separation reheater 26 through the high-pressure cylinder first-stage steam extraction valve bank 25; opening a stop valve in the main steam supply steam-water separation reheater valve bank 27, and adjusting the amount of steam entering a secondary reheater of the steam-water separation reheater 26 through the main steam supply steam-water separation reheater valve bank 27;
7a) after the steam turbine is loaded, when the steam extraction pressure of the steam turbine low pressure cylinder 4 is close to the rated pressure of the steam side of the low pressure heater 8, the low pressure cylinder steam extraction valve group 19 is opened, the main steam bypass is gradually closed to supply the low pressure heater valve group 20, and the steam amount entering the low pressure heater 8 is adjusted through the low pressure cylinder steam extraction valve group 19 to control the water temperature at the outlet of the low pressure heater 8;
8a) when the steam pressure at the high-pressure cylinder steam exhaust and deaerator valve bank 22 is close to the rated pressure of the deaerator 9, a stop valve in the high-pressure cylinder steam exhaust and deaerator valve bank 22 is opened, the amount of steam entering the deaerator 9 is adjusted through the high-pressure cylinder steam exhaust and deaerator valve bank 22, and a main steam bypass and deaerator valve bank 21 is gradually closed to control the water temperature at the outlet of the deaerator 9;
9a) the reactor is used for increasing power, the steam turbine continues to increase load, when the steam extraction pressure of the steam turbine high and medium pressure cylinder 3 is close to the rated pressure of the steam side of the high-pressure heater 11, the high-pressure cylinder steam extraction supply high-pressure heater valve group 23 is opened, the main steam bypass high-pressure heater valve group 24 is gradually closed, the amount of steam entering the high-pressure heater 11 is adjusted through the high-pressure cylinder steam extraction high-pressure heater valve group 23, and the water temperature at the outlet of the high-pressure heater 11 is controlled;
10a) along with the increase of the load of the steam turbine, the main steam bypass valve group 18 is gradually closed, after the steam turbine carries high load, the shaft seal system reaches a self-sealing state, the main steam supply shaft seal system valve group 13 is closed, the reactor is lifted to full power, the steam turbine carries full load operation, and the start of the second loop is finished;
the specific process of normal stop of the second loop is as follows:
1b) in the process of stopping the second loop, reducing the power of the reactor, reducing the load of the steam turbine, opening a main steam bypass high-pressure heater valve group 24 when the steam extraction pressure of a steam turbine high-pressure and medium-pressure cylinder 3 is smaller than the rated pressure of the steam side of the high-pressure heater 11, gradually closing a high-pressure cylinder steam extraction high-pressure heater valve group 23, and adjusting the steam amount entering the high-pressure heater 11 through the main steam bypass high-pressure heater valve group 24 so as to control the water temperature at the outlet of the high-pressure heater 11;
2b) when the pressure at the inlet of the high-pressure cylinder exhaust steam supply deaerator valve set 22 is smaller than the rated pressure of the deaerator 9, opening a stop valve in the main steam bypass deaerator valve set 21, adjusting the steam amount entering the deaerator 9 through the main steam bypass deaerator valve set 21, and gradually closing the high-pressure cylinder exhaust steam supply deaerator valve set 22;
3b) as the load of the steam turbine continues to be reduced, when the steam extraction pressure of the steam turbine low pressure cylinder 4 is smaller than the rated pressure of the steam side of the low pressure heater 8, the main steam bypass low pressure heater valve group 20 is opened, the amount of steam entering the low pressure heater 8 is adjusted through the main steam bypass low pressure heater valve group 20, so as to control the water temperature at the outlet of the low pressure heater 8, and the low pressure cylinder steam extraction valve group 19 is gradually closed;
4b) after the load of the steam turbine is reduced, opening a main steam shaft seal supply system valve group 13, putting a shaft seal steam supply system 14, opening a main steam bypass valve group 18, and controlling the pressure of a main steam main pipe to be stable through the main steam bypass valve group 18 until the load of the steam turbine is reduced to zero load; and (3) exiting the moisture separator reheater 26, and closing the high-pressure cylinder first-section steam extraction valve bank 25, the main steam supply moisture separator reheater valve bank 27, the moisture separator reheater inlet valve bank 28 and the moisture separator reheater outlet valve bank 29.
The specific process of the unit shutdown without shutdown operation is as follows:
1c) after the emergency trip of the steam turbine, closing a steam inlet valve bank 2 of the steam turbine, a primary steam extraction valve bank 25 of a high-pressure cylinder, a main steam supply steam-water separation reheater valve bank 27, a steam-water separation reheater inlet valve bank 28 and a steam-water separation reheater outlet valve bank 29, stopping steam inlet of the steam turbine, and cutting off a steam-water separation reheater 26; opening a main steam supply shaft seal system valve group 13, and putting a shaft seal steam supply system 14; opening a main steam bypass valve group 18, adjusting the pressure stability of a main steam main pipe through the main steam bypass valve group 18, starting the turbine to idle, and reducing the rotating speed of the turbine;
2c) closing the low-pressure cylinder steam extraction valve set 19, opening the main steam bypass for the low-pressure heater valve set 20, and stabilizing the water temperature at the outlet of the low-pressure heater 8; closing the high-pressure cylinder exhaust steam supply deaerator valve set 22, opening the main steam bypass supply deaerator valve set 21, and stabilizing the water temperature at the outlet of the deaerator 9;
3c) closing a high-pressure cylinder steam extraction and supply high-pressure heater valve group 23, opening a main steam bypass high-pressure heater valve group 24, absorbing the waste heat of main steam by the high-pressure heater 11, stabilizing the water temperature at the outlet of the high-pressure heater 11, and keeping the water temperature at the inlet of the steam generator 1 stable;
4c) the rotating speed of the steam turbine is reduced to zero, turning is carried out, the temperature of the feed water of the two loops is stable, and the reactor runs at low power.
Claims (4)
1. The self-adaptive steam supply system for the two-loop thermodynamic system of the pressurized water reactor nuclear power unit is characterized by comprising a steam generator (1), a steam turbine high-pressure and medium-pressure cylinder (3), a steam turbine low-pressure cylinder (4), a generator set (5), a condenser (6), a low-pressure heater (8), a deaerator (9), a high-pressure heater (11), a shaft seal steam supply system (14), a steam-water separation reheater (26), a steam turbine steam inlet valve bank (2), a main steam supply valve bank (12), a main steam supply shaft seal system valve bank (13), a high-pressure cylinder one-section steam extraction valve bank (25), a main steam supply steam-water separation reheater valve bank (27), a steam-water separation reheater inlet valve bank (28) and a steam-water separation reheater outlet valve bank (29), an auxiliary steam system (16), an auxiliary steam supply system valve bank (15), an auxiliary, A main steam bypass valve bank (18), a low-pressure cylinder steam extraction valve bank (19), a main steam bypass low-pressure heater valve bank (20), a main steam bypass deaerator valve bank (21), a high-pressure cylinder steam exhaust deaerator valve bank (22), a high-pressure cylinder steam extraction high-pressure heater valve bank (23) and a main steam bypass high-pressure heater valve bank (24);
the secondary side outlet of the steam generator (1) is divided into three paths, wherein the first path is communicated with the inlet of the steam inlet valve group (2) of the steam turbine, the second path is communicated with the inlet of the main steam supply valve group (12), and the third path is communicated with one end of a main steam bypass;
the outlet of the steam turbine steam inlet valve group (2) is communicated with the inlet of a steam turbine high and medium pressure cylinder (3), the steam turbine high and medium pressure cylinder (3), a steam turbine low pressure cylinder (4) and a generator set (5) are connected, the steam exhaust port of the steam turbine high and medium pressure cylinder (3) is divided into two paths, one path of the steam-water separation reheater is communicated with an inlet of a steam-water separation reheater (26) through a steam-water separation reheater inlet valve bank (28), the other path of the steam-water separation reheater is communicated with an inlet of a deaerator valve bank (22) through high-pressure cylinder exhaust steam, an outlet of the steam-water separation reheater (26) is communicated with an inlet of a steam turbine low-pressure cylinder (4) through a steam-water separation reheater outlet valve bank (29), an exhaust steam port of the steam turbine low-pressure cylinder (4) is communicated with an inlet of a condenser (6), and an outlet of the condenser (6) is communicated with a secondary side inlet of the steam generator (1) through a low-pressure heater (8), a deaerator;
the outlet of the main steam supply valve bank (12) is divided into two paths, one path is communicated with the inlet of a secondary reheater of the steam-water separation reheater (26) through a main steam supply steam-water separation reheater valve bank (27), and the other path is communicated with a shaft seal steam supply system (14) through a main steam supply shaft seal system valve bank (13); a section of steam extraction port of the high-pressure cylinder in the high-medium pressure cylinder (3) of the steam turbine is communicated with a first-stage reheater inlet of a steam-water separation reheater (26) through a section of steam extraction valve bank (25) of the high-pressure cylinder;
the outlet of the auxiliary steam system (16) is divided into two paths, one path is communicated with the inlet of a shaft seal steam supply system (14) through an auxiliary steam supply shaft seal system valve group (15), the other path is communicated with the inlet of a deaerator (9) through an auxiliary steam supply deaerator valve group (17), the steam exhaust port of a high and medium pressure cylinder (3) of the steam turbine is communicated with the inlet of a high pressure cylinder steam exhaust deaerator valve group (22), the other end of a main steam bypass is communicated with the inlet of a main steam bypass supply high pressure heater valve group (24) and the inlet of a main steam bypass supply deaerator valve group (21), the inlet of the main steam bypass low-pressure heater valve group (20) is communicated with the inlet of the main steam bypass valve group (18), the steam extraction port of the turbine high-intermediate pressure cylinder (3) is communicated with the inlet of the high-pressure cylinder steam extraction high-pressure heater valve group (23), and the steam extraction port of the turbine low-pressure cylinder (4) is communicated with the inlet of the low-pressure cylinder steam extraction valve group (19);
an outlet of the high-pressure cylinder steam extraction and supply high-pressure heater valve group (23) and an outlet of the main steam bypass and supply high-pressure heater valve group (24) are communicated with an inlet of the high-pressure heater (11) through pipelines and pipes;
an outlet of the main steam bypass deaerator valve bank (21) and an outlet of the high-pressure cylinder steam exhaust deaerator valve bank (22) are communicated with an inlet of a deaerator (9) through a pipeline after being connected in parallel;
the outlet of the low-pressure cylinder steam extraction valve group (19) is communicated with the outlet of the main steam bypass low-pressure heater valve group (20) through a pipeline and a pipe and then is communicated with the inlet of the low-pressure heater (8).
2. The pressurized water reactor nuclear power unit secondary loop thermodynamic system self-adaptive steam supply system according to claim 1, wherein an outlet of the condenser (6) is communicated with an inlet of the low-pressure heater (8) through a condensate pump (7).
3. The pressurized water reactor nuclear power unit secondary loop thermodynamic system self-adaptive steam supply system according to claim 1, wherein the turbine high and medium pressure cylinder (3), the turbine low pressure cylinder (4) and the generator set (5) are coaxially connected.
4. The pressurized water reactor nuclear power unit secondary loop thermodynamic system self-adaptive steam supply system according to claim 1, wherein an outlet of the deaerator (9) is communicated with an inlet of the high-pressure heater (1) through a water feed pump (10).
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| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
| CN110259532A (en) * | 2019-07-10 | 2019-09-20 | 西安热工研究院有限公司 | The adaptive steam-supplying system of secondary circuit of PWR nuclear power plant therrmodynamic system and method |
| CN112177695A (en) * | 2020-09-29 | 2021-01-05 | 西安热工研究院有限公司 | Small pressurized water reactor power generation system adopting micro superheated steam |
| CN117524524A (en) * | 2023-11-21 | 2024-02-06 | 华能山东石岛湾核电有限公司 | Shutdown non-shutdown system for high-temperature gas cooled reactor |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
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| CN110259532A (en) * | 2019-07-10 | 2019-09-20 | 西安热工研究院有限公司 | The adaptive steam-supplying system of secondary circuit of PWR nuclear power plant therrmodynamic system and method |
| CN112177695A (en) * | 2020-09-29 | 2021-01-05 | 西安热工研究院有限公司 | Small pressurized water reactor power generation system adopting micro superheated steam |
| CN117524524A (en) * | 2023-11-21 | 2024-02-06 | 华能山东石岛湾核电有限公司 | Shutdown non-shutdown system for high-temperature gas cooled reactor |
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