CN116230263A - Nuclear power station spent fuel pool waste heat utilization system - Google Patents
Nuclear power station spent fuel pool waste heat utilization system Download PDFInfo
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- CN116230263A CN116230263A CN202111461446.0A CN202111461446A CN116230263A CN 116230263 A CN116230263 A CN 116230263A CN 202111461446 A CN202111461446 A CN 202111461446A CN 116230263 A CN116230263 A CN 116230263A
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- spent fuel
- fuel pool
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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Abstract
The invention relates to the technical field of nuclear power waste heat utilization, in particular to a nuclear power station spent fuel pool waste heat utilization system. Comprising the following steps: the nuclear turbine thermodynamic system is used for providing steam, condensing the steam through a condenser to form condensate, and exchanging heat in the spent fuel pool waste heat exchange system; the spent fuel pool waste heat exchange system exchanges heat by utilizing the condensation water flowing through the spent fuel pool waste heat exchanger and the heat generated by decay of the spent fuel in the spent fuel pool, and the heat is transferred to the condensation water, so that the temperature of the condensation water is increased; the spent fuel pool cooling system is used for transmitting the waste heat of the spent fuel pool to equipment cooling water through a heat exchanger; the equipment cooling water loop system transfers heat absorbed by equipment when the equipment is cooled to the sea water. The advantages are that: the condensate water is used as a main cooling water source of the spent fuel pool, so that the utilization of the decay waste heat of the spent fuel is realized, the temperature of the condensate water is increased, and the heat consumption rate of a thermodynamic system of the steam turbine is reduced.
Description
Technical Field
The invention relates to the technical field of nuclear power waste heat utilization, in particular to a nuclear power station spent fuel pool waste heat utilization system.
Background
At present, a spent fuel pool of a nuclear power plant is used as a storage place of spent fuel, the spent fuel decays to generate heat, the spent fuel pool is cooled by means of equipment cooling water, the equipment cooling water absorbs decay heat of the spent fuel through a spent fuel pool heat exchanger, and after heat exchange is carried out between the spent fuel pool heat exchanger and sea water, the heat of the spent fuel decays is finally transferred to the sea water, and the sea water is discharged into the ocean again. Therefore, the waste heat after the spent fuel in the spent fuel pool of the nuclear power station decays is not effectively utilized, and heat loss is caused.
Disclosure of Invention
Aiming at the problems existing in the prior art, the invention aims to provide a nuclear power station spent fuel pool waste heat utilization system which can effectively utilize waste heat after spent fuel in a spent fuel pool decays and increase the safety of the spent fuel pool.
The technical scheme of the invention is as follows: a nuclear power plant spent fuel pool waste heat utilization system, comprising: the nuclear turbine thermodynamic system, the spent fuel pool waste heat exchange system, the spent fuel pool cooling system and the equipment cooling water loop system, wherein: the nuclear turbine thermodynamic system is used for providing steam, condensing the steam through a condenser to form condensate water, and exchanging heat in the spent fuel pool waste heat exchange system; the spent fuel pool waste heat exchange system exchanges heat by utilizing the condensation water flowing through the spent fuel pool waste heat exchanger and the heat generated by decay of the spent fuel in the spent fuel pool, and the heat is transferred to the condensation water, so that the temperature of the condensation water is increased; the spent fuel pool cooling system is used for transmitting the waste heat of the spent fuel pool to equipment cooling water through a heat exchanger; the equipment cooling water loop system transfers heat absorbed by equipment when the equipment is cooled to the sea water.
The nuclear turbine thermodynamic system comprises a turbine unit, a condenser, a condensate pump, a low-pressure heater, a deaerator, a main water supply pump set, a high-pressure heater, a steam generator and a generator; the steam turbine is used for converting heat energy of steam generated by the steam generator into kinetic energy of the steam turbine unit, the condenser is used for condensing exhaust steam which does work of the steam turbine unit to form condensate, the condensate pump is used for providing kinetic energy for condensate of the nuclear turbine thermodynamic system and the spent fuel pool waste heat exchange system, the low-pressure heater is used for heating the condensate flowing through the condensate, the deaerator is used for fully mixing the condensate through atomization or spraying and heating the steam and removing insoluble oxygen or other non-condensable gas in the condensate, the main water supply pump unit is used for providing kinetic energy for circulation in the nuclear turbine thermodynamic system, the high-pressure heater is used for heating water flowing through the main water supply pump unit, the steam generator is used for performing heat exchange and simultaneously playing a role of blocking a radioactive heat carrier, and the generator is used for converting rotational kinetic energy of the steam turbine unit into electric energy.
And the condensate water provided by the nuclear turbine thermodynamic system is boosted by the condensate water pump and then enters the spent fuel pool waste heat exchanger, the condensate water exchanges heat with the spent fuel pool water, and then is mixed with the condensate water shunted by the electric flow regulating valve of the spent fuel pool waste heat exchanger after passing through the electric isolating valve of the spent fuel pool waste heat exchanger, and returns to the nuclear turbine thermodynamic system, and the electric isolating valve is arranged at the inlet and outlet of the spent fuel pool waste heat exchanger.
The inlet and outlet of the spent fuel pool waste heat exchanger are provided with a radioactive substance monitoring instrument.
The spent fuel pool waste heat exchange system is provided with a flow regulating station.
The spent fuel pool waste heat exchange system is provided with a waste heat exchanger regulating station bypass.
The equipment cooling water loop system is connected with the spent fuel pool waste heat exchange system in parallel and is used as a standby cooling water source for cooling the spent fuel pool when the nuclear turbine thermodynamic system accident situation, the water temperature of the spent fuel pool exceeds the limit value or the operation parameters of the spent fuel pool waste heat exchanger do not meet the requirements.
The equipment cooling water loop system is used for transferring the decay heat of the spent fuel to the sea water.
The invention has the beneficial effects that: according to the spent fuel pool waste heat utilization system of the nuclear power station, the condensate water is used as a main cooling water source of the spent fuel pool, so that the utilization of spent fuel decay waste heat is realized, the temperature of the condensate water is increased, the heat consumption rate of a thermal system of a steam turbine is reduced, and the thermal economy of the steam turbine of the nuclear power station is improved.
The invention reduces the emission of decay heat of the spent fuel pool fuel to the ocean, correspondingly reduces the thermal pollution effect on the ocean environment and reduces the adverse effect on the local ocean ecological environment.
The cooling water loop system of the equipment is used as a standby cooling system, so that the diversity of cooling water sources is increased, and the safety of the spent fuel pool is improved.
The invention is beneficial to providing a stable turbine condensate temperature and reducing the influence of external natural environment factors on condensate.
Drawings
Fig. 1 is a schematic diagram of a nuclear power station spent fuel pool waste heat utilization system provided by the invention.
In the figure: the system comprises a nuclear turbine thermodynamic system, a spent fuel pool waste heat exchange system, a spent fuel pool cooling system, a 4-equipment cooling water loop system, a 101 turbine, a 102 condenser, a 103 condensate pump, a 104 low-pressure heater, a 105 deaerator, a 106 main water supply pump set, a 107 high-pressure heater, a 108 steam generator, a 109 generator, a 201 spent fuel pool waste heat exchanger, a 202 waste heat exchanger regulating station bypass electric isolation valve, a 203 waste heat exchanger flow electric regulating valve, a 204 waste heat exchanger flow regulating valve front manual isolation valve, a 205 waste heat exchanger flow regulating valve rear manual isolation valve, a 206 waste heat exchanger front electric isolation valve, a 207 waste heat exchanger rear electric isolation valve, a 208 waste heat exchanger inlet flow measurement point, a 209 waste heat exchanger inlet temperature measurement point, a 210 waste heat exchanger inlet radioactive material detection measurement point, a 212 waste heat exchanger outlet radioactive material detection measurement point, a 213 waste heat exchanger outlet flow measurement point, a 301 spent fuel pool cooling water pump, a 302 waste fuel side waste heat exchanger front electric isolation valve, a 303 spent fuel pool side waste heat exchanger rear electric isolation valve 401 equipment cooling water heat exchanger, a 402 equipment cooling water heat exchanger front electric isolation valve 403, and a post-equipment cooling water heat exchanger cooling valve.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
As shown in fig. 1, the system for utilizing waste heat of spent fuel pool in nuclear power station provided by the invention comprises: a nuclear turbine thermodynamic system 1; the spent fuel pool waste heat exchange system 2; a spent fuel pool cooling system 3; a plant cooling water circuit system 4.
The nuclear turbine thermodynamic system 1 comprises a turbine unit 101, a condenser 102, a condensate pump 103, a low-pressure heater 104, a deaerator 105, a main water supply pump group 106, a high-pressure heater 107, a steam generator 108 and a generator 109. The steam turbine 101 is configured to convert thermal energy of steam generated by the steam generator 108 into kinetic energy of the turbine set 101. The condenser 102 is used for condensing the exhaust steam which is done by the turbine unit 101 to form condensed water. The condensate pump 103 is used for providing kinetic energy for condensate water of the nuclear turbine thermodynamic system 1 and the spent fuel pool waste heat exchange system 2. The low pressure heater 104 is used to heat the condensed water flowing therethrough. The deaerator 105 is used to thoroughly mix the condensate by atomizing or spraying and heating the steam, and to remove the insoluble oxygen or other non-condensable gases from the condensate to the desired water quality. The main water supply pump group 106 is used for providing kinetic energy for circulation in the thermodynamic system 1 of the nuclear turbine. The high pressure heater 107 is used to heat the feedwater flowing therethrough. The steam generator 108 is used for heat exchange and also serves as a barrier to the radioactive heat carrier. The generator 109 is used to convert kinetic energy generated by the turbine unit 101 into electrical energy.
The spent fuel pool waste heat exchange system 2 comprises a spent fuel pool waste heat exchanger 201, a waste heat exchanger regulating station bypass electric isolation valve 202, a waste heat exchanger flow electric regulating valve 203, a waste heat exchanger flow regulating valve front manual isolation valve 204, a waste heat exchanger flow regulating valve rear manual isolation valve 205, a waste heat exchanger front electric isolation valve 206 and a waste heat exchanger rear electric isolation valve 207. The device is connected with a condensate pump through a pipeline, the condensate pump 103 is boosted and then enters the spent fuel pool waste heat exchanger 201 through the front manual isolation valve 206 of the waste heat exchanger, after the condensate water exchanges heat with the spent fuel pool through the waste heat exchanger 201, the condensate water absorbing heat flows out through the rear manual isolation valve 207 of the waste heat exchanger, and is mixed with the condensate water flowing through the electric flow regulating valve 203 of the waste heat exchanger and then returns to the heating system 1 of the nuclear turbine.
The spent fuel pool waste heat exchange system 2 monitors the waste heat exchanger inlet flow measuring point 208 and the waste heat exchanger outlet flow measuring point 213, and if the deviation between 208 and 213 is large, the spent fuel pool waste heat exchange system 2 should be checked immediately to avoid condensate leaking into the spent fuel pool.
When the electric flow regulating valve 203 of the spent fuel pool waste heat exchanger fails, the bypass electric isolation valve 202 of the waste heat exchanger regulating station is opened, so that the operation of the nuclear turbine thermodynamic system 1 is prevented from being influenced by the failure, the load of the nuclear power plant is limited, and the spent fuel pool waste heat exchanger 201 is stopped. And opening the front electric isolation valve 402 of the equipment cooling water heat exchanger and the rear electric isolation valve 403 of the equipment cooling water heat exchanger, and switching the spent fuel pool waste heat exchange system 2 into the equipment cooling water loop system 4 to operate.
In the adjustment process of the electric flow regulating valve 203 of the spent fuel pool waste heat exchanger, the temperature change of the spent fuel pool is considered, and the supercooling phenomenon of the spent fuel pool is avoided.
The design of the pipeline of the electric flow regulating valve 203 of the spent fuel pool waste heat exchanger and the pipeline of the bypass electric isolation valve 202 of the waste heat exchanger regulating station should meet the condensate flow requirement required by the nuclear turbine thermodynamic system 1 when the spent fuel pool waste heat exchanger 201 is in an isolated state.
The front electric isolating valve 206 of the waste heat exchanger and the rear electric isolating valve 207 of the waste heat exchanger are used for isolating the waste heat exchanger 201 of the spent fuel pool from a system during maintenance or isolating the waste heat exchanger of the spent fuel pool during emergency.
The spent fuel pool cooling system 3 uses the spent fuel pool cooling water pump 301 to transfer the working medium which absorbs the decay heat of the spent fuel in the spent fuel pool to the spent fuel pool waste heat exchanger 201 for heat exchange through the kinetic energy provided by the working medium, and the working medium after heat release returns to the spent fuel pool. When the accident situation of the nuclear turbine thermodynamic system 1, the water temperature of the spent fuel pool exceeds the limit value or the operation parameters of the spent fuel pool waste heat exchanger 201 are not satisfied, the spent fuel pool cooling water pump 301 sends the working medium which absorbs the decay heat of the spent fuel in the spent fuel pool to the equipment cooling water loop system 4 for cooling.
The spent fuel pool cooling water system 3, the spent fuel pool waste heat exchanger 201 and the equipment cooling water heat exchanger 401 allow short-time parallel connection, such as high spent fuel pool temperature, and the spent fuel pool waste heat exchange system 2 is switched to the equipment cooling water loop system 4 to operate.
The spent fuel pool waste heat exchange system 2, the equipment cooling water loop system 4 and all structures and equipment meet the nuclear safety level requirements so as to prevent radioactive fission products from escaping;
the spent fuel pool waste heat exchanger 201, the condensate pressure must be greater than the spent fuel water pressure; the plant cooling water heat exchanger must have a plant cooling water pressure greater than the spent fuel water pressure.
An inlet temperature measuring point 209 of the waste heat exchanger is arranged on an inlet pipeline of the front electric isolating valve 206 of the waste heat exchanger and is used for monitoring the condensation water temperature condition in the waste heat exchange system 2 of the spent fuel pool. The waste heat exchanger inlet flow measurement point 208 is used for monitoring the water flow rate of condensation flowing through the spent fuel pool waste heat exchanger 201.
The pipeline at the outlet of the electric isolating valve 207 behind the waste heat exchanger is provided with a waste heat exchanger outlet temperature measuring point 212 for monitoring the temperature rise condition of the condensed water after the condensed water flows through the waste heat exchanger 201 of the spent fuel pool and exchanges heat with the spent fuel pool.
The radioactive substance detection measuring point 210 at the inlet of the waste heat exchanger and the radioactive substance detection measuring point 211 at the outlet of the waste heat exchanger are used for monitoring the radiation condition of condensed water after heat absorption. If the radiation substances are detected, the nuclear power station instrument control protection quick-closing electric isolation valve 206 before the waste heat exchanger and the electric isolation valve 207 after the waste heat exchanger are closed, so that the operation of the spent fuel pool waste heat exchanger 201 is exited, and meanwhile, the electric isolation valve 402 before the equipment cooling water heat exchanger and the electric isolation valve 403 after the equipment cooling water heat exchanger are opened in an interlocking manner and are switched to the operation of the equipment cooling water loop system 4.
While embodiments of the present invention have been shown and described, it will be understood by those of ordinary skill in the art that modifications may be made to these embodiments to secure the operation of the present invention without departing from the principles of the invention, the scope of which is defined in the appended claims and their equivalents.
Claims (8)
1. A nuclear power plant spent fuel pool waste heat utilization system, comprising: the nuclear turbine thermodynamic system, the spent fuel pool waste heat exchange system, the spent fuel pool cooling system and the equipment cooling water loop system, wherein: the nuclear turbine thermodynamic system is used for providing steam, condensing the steam through a condenser to form condensate water, and exchanging heat in the spent fuel pool waste heat exchange system; the spent fuel pool waste heat exchange system exchanges heat by utilizing the condensation water flowing through the spent fuel pool waste heat exchanger and the heat generated by decay of the spent fuel in the spent fuel pool, and the heat is transferred to the condensation water, so that the temperature of the condensation water is increased; the spent fuel pool cooling system is used for transmitting the waste heat of the spent fuel pool to equipment cooling water through a heat exchanger; the equipment cooling water loop system transfers heat absorbed by equipment when the equipment is cooled to the sea water.
2. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the nuclear turbine thermodynamic system comprises a turbine unit, a condenser, a condensate pump, a low-pressure heater, a deaerator, a main water supply pump set, a high-pressure heater, a steam generator and a generator; the steam turbine is used for converting heat energy of steam generated by the steam generator into kinetic energy of the steam turbine unit, the condenser is used for condensing exhaust steam which does work of the steam turbine unit to form condensate, the condensate pump is used for providing kinetic energy for condensate of the nuclear turbine thermodynamic system and the spent fuel pool waste heat exchange system, the low-pressure heater is used for heating the condensate flowing through the condensate, the deaerator is used for fully mixing the condensate through atomization or spraying and heating the steam and removing insoluble oxygen or other non-condensable gas in the condensate, the main water supply pump unit is used for providing kinetic energy for circulation in the nuclear turbine thermodynamic system, the high-pressure heater is used for heating water flowing through the main water supply pump unit, the steam generator is used for performing heat exchange and simultaneously playing a role of blocking a radioactive heat carrier, and the generator is used for converting rotational kinetic energy of the steam turbine unit into electric energy.
3. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: and the condensate water provided by the nuclear turbine thermodynamic system is boosted by the condensate water pump and then enters the spent fuel pool waste heat exchanger, the condensate water exchanges heat with the spent fuel pool water, and then is mixed with the condensate water shunted by the electric flow regulating valve of the spent fuel pool waste heat exchanger after passing through the electric isolating valve of the spent fuel pool waste heat exchanger, and returns to the nuclear turbine thermodynamic system, and the electric isolating valve is arranged at the inlet and outlet of the spent fuel pool waste heat exchanger.
4. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the inlet and outlet of the spent fuel pool waste heat exchanger are provided with a radioactive substance monitoring instrument.
5. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the spent fuel pool waste heat exchange system is provided with a flow regulating station.
6. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the spent fuel pool waste heat exchange system is provided with a waste heat exchanger regulating station bypass.
7. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the equipment cooling water loop system is connected with the spent fuel pool waste heat exchange system in parallel and is used as a standby cooling water source for cooling the spent fuel pool when the nuclear turbine thermodynamic system accident situation, the water temperature of the spent fuel pool exceeds the limit value or the operation parameters of the spent fuel pool waste heat exchanger do not meet the requirements.
8. The nuclear power plant spent fuel pool waste heat utilization system according to claim 1, wherein: the equipment cooling water loop system is used for transferring the decay heat of the spent fuel to the sea water.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202111461446.0A CN116230263A (en) | 2021-12-03 | 2021-12-03 | Nuclear power station spent fuel pool waste heat utilization system |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111461446.0A CN116230263A (en) | 2021-12-03 | 2021-12-03 | Nuclear power station spent fuel pool waste heat utilization system |
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| CN116230263A true CN116230263A (en) | 2023-06-06 |
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| CN202111461446.0A Pending CN116230263A (en) | 2021-12-03 | 2021-12-03 | Nuclear power station spent fuel pool waste heat utilization system |
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