CN112289472A - Passive water replenishing system of steam generator for passive nuclear power plant - Google Patents

Passive water replenishing system of steam generator for passive nuclear power plant Download PDF

Info

Publication number
CN112289472A
CN112289472A CN202011299269.6A CN202011299269A CN112289472A CN 112289472 A CN112289472 A CN 112289472A CN 202011299269 A CN202011299269 A CN 202011299269A CN 112289472 A CN112289472 A CN 112289472A
Authority
CN
China
Prior art keywords
steam generator
passive
water supply
starting
water
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202011299269.6A
Other languages
Chinese (zh)
Inventor
缪正强
马柏松
程昭
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Shandong Nuclear Power Co Ltd
Original Assignee
Shandong Nuclear Power Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Shandong Nuclear Power Co Ltd filed Critical Shandong Nuclear Power Co Ltd
Priority to CN202011299269.6A priority Critical patent/CN112289472A/en
Publication of CN112289472A publication Critical patent/CN112289472A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/04Pumping arrangements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The invention discloses a passive water replenishing system of a steam generator for a passive nuclear power plant, which further comprises the passive water replenishing system of the steam generator on the basis of a starting water supply system, wherein the passive water replenishing system of the steam generator comprises a heat exchanger and a pressure accumulation box, the heat exchanger is arranged in a condensation water tank, the bottom elevation of the condensation water tank is higher than the top elevation of the steam generator, a steam pipeline at the inlet of the heat exchanger is connected with the steam generator and a main steam pipeline, and an outlet pipeline of the heat exchanger is connected with a starting water supply main pipe; a certain amount of cooling water is stored in the pressure accumulation box, high-pressure nitrogen is arranged in the pressure accumulation box to maintain pressure, and the outlet of the pressure accumulation box is connected to a starting water supply main pipe through an electric valve.

Description

Passive water replenishing system of steam generator for passive nuclear power plant
Technical Field
The invention relates to a passive water replenishing system of a steam generator for a passive nuclear power plant, wherein the passive nuclear power plant refers to a nuclear power plant adopting the technologies of AP1000, CAP1400 and the like.
Background
After the reactor is shut down, the heat generated by fission reaction caused by neutrons in a short period of time, decay of fission products and the like still needs to be discharged in a long period of time, otherwise, the serious accident of coolant boiling and even core melting can be caused. In the design of a pressurized water reactor nuclear power plant, a steam generator is supplemented with water in an active mode, and under the condition that power supply is guaranteed, a water supply pump drives the secondary side of the steam generator to supply water for forced circulation, so that the waste heat of a reactor core is led out and sent to a final hot trap.
In nuclear power plants such as AP1000, CAP1400, etc., the steam generators 15 and 16 are supplied with water and maintained at a level by a startup water supply system under certain operating conditions. If the liquid level is reduced to a certain setting value due to the fact that the liquid level cannot be maintained successfully, a passive core cooling system of the power plant is started to discharge the core decay heat in a passive mode in an emergency mode. The startup of the passive core cooling system is limited in the service life of the power plant, so that unnecessary startup is reduced as much as possible.
As shown in fig. 1, two startup water feed pumps 2 and 3 suck water from a condensate tank 1, respectively flow through check valves 4 and 5 and isolation valves 6 and 7, and then are collected in a startup water feed main pipe 8, and flow through startup water feed adjusting valves 9 and 10, startup water feed check valves 11 and 12, and startup water feed isolation valves 13 and 14, and then supply water to two steam generators 15 and 16.
Disclosure of Invention
The invention aims to solve the technical problems that two starting water-feeding pumps in the prior art are electric pumps, the operation needs the support of an alternating current power supply, and under the whole-plant power-off working condition (the failure of a standby diesel generating set due to the superposition of an external alternating current power supply), the starting water-feeding pumps cannot be started, and a starting water-feeding system cannot maintain the liquid level of a steam generator, so that a passive core cooling system is started.
In order to solve the technical problems, the technical scheme of the invention provides a passive water replenishing system of a steam generator for a passive nuclear power plant, which comprises a starting water supply system, wherein the starting water supply system comprises two starting water supply pumps, the two starting water supply pumps suck water from a condensation water tank, the water is collected to a starting water supply main pipe after flowing through corresponding check valves and isolation valves respectively, and then the water is supplied to the two steam generators after flowing through corresponding starting water supply regulating valves, starting water supply check valves and starting water supply isolation valves respectively;
the system is characterized by further comprising a steam generator passive water replenishing system on the basis of starting a water supply system, wherein the steam generator passive water replenishing system comprises a heat exchanger and a pressure accumulation box, the heat exchanger is arranged in a condensation water tank, the bottom elevation of the condensation water tank is higher than the top elevation of the steam generator, a steam pipeline at the inlet of the heat exchanger is connected with a main steam pipeline of the steam generator, and an outlet pipeline of the heat exchanger is connected with a starting water supply main pipe; a certain amount of cooling water is stored in the pressure accumulation box, high-pressure nitrogen is stored in the pressure accumulation box to maintain pressure, and the outlet of the pressure accumulation box is connected to a starting water supply main pipe through an electric valve.
Wherein, a pneumatic valve is arranged on the outlet pipeline of the heat exchanger.
The invention has the advantages that:
1. when a secondary loop water supply system of the passive pressurized water reactor nuclear power plant breaks down, the liquid level of the steam generator is maintained through the passive water supply system, the waste heat of the reactor core is led out, the dependence on a passive reactor core cooling system is reduced, unnecessary starting of the passive reactor core cooling system is reduced, and the starting times are reduced.
2. The heat exchanger and the pressure storage box are automatically put into operation, so that the possibility of human error is reduced.
3. The reliability of the water supply of the two loops is improved, and the damage probability of the reactor core and the probability of releasing a large amount of radioactivity to the environment are reduced.
Drawings
FIG. 1 is a prior art startup water supply system;
reference numbers in the figures: the system comprises a condensation water tank 1, a starting feed pump 2, a starting feed pump 3, a check valve 4, a check valve 5, an isolation valve 6, an isolation valve B7, a starting feed main pipe 8, a starting feed adjusting valve A9, a starting feed adjusting valve 10, a check valve 11, a check valve 12, a starting feed isolation valve 13, a starting feed isolation valve 14, a steam generator 15, a steam generator 16, a steam isolation valve 17 and a steam isolation valve 18;
FIG. 2 is a schematic view of an improved passive water replenishment system for a steam generator according to the present invention;
reference numbers in the figures: the system comprises a condensation water tank 1, a starting feed water pump 2, a starting feed water pump 3, a check valve 4, a check valve 5, an isolation valve 6, an isolation valve B7, a starting feed water main pipe 8, a starting feed water adjusting valve 9, a starting feed water adjusting valve 10, a check valve 11, a check valve 12, a starting feed water isolation valve 13, a starting feed water isolation valve 14, a steam generator 15, a steam generator 16, a steam isolation valve 17, a steam isolation valve 18, a pressure storage tank 21, an isolation valve 22, an isolation valve 31, a heat exchanger 32, an air-operated valve 33 and a check valve 34.
Detailed Description
In order to make the invention more comprehensible, preferred embodiments are described in detail below with reference to the accompanying drawings.
Examples
In the embodiment, a passive water replenishing system of the steam generator is additionally arranged on the basis of starting the water supply system, as shown in figure 2.
1. The condensation water tank 1 is placed at a high position, and the elevation of the bottom of the water tank is at least higher than the elevation of the top of the steam generator.
2. A heat exchanger 32 is arranged in the condensation water tank 1, a steam pipeline at the inlet of the heat exchanger 32 is connected with main steam pipelines of the steam generators 15 and 16, and an outlet pipeline of the heat exchanger is connected with a starting water supply main pipe 8.
3. The pressure accumulation box 21 is additionally arranged, a certain amount of cooling water is stored in the pressure accumulation box, the water quality is consistent with that of the condensation water tank, and the pressure of the condensation water tank is maintained by high-pressure nitrogen. In addition, an electrically operated valve 22 is provided at the outlet of the accumulator tank, as shown.
When the liquid levels of the steam generators 15 and 16 are lower than a certain set value and the water supply provided by the electric starting water supply pumps 2 and 3 is lost (under the whole plant power-off working condition) or is expected to be lost (the external alternating current power supply is lost and the standby diesel generating set is about to stop running), the steam isolation valves 17 and 18 are closed in time, the pneumatic valve 33 is opened, the heat exchanger 32 is put into operation, so that condensed water after steam condensation is injected into the two steam generators 15 and 16 again through the starting water supply main pipe 8, heat is absorbed for vaporization, the decay heat source is continuously led out to the condensation water tank 1, and meanwhile, the water content in the whole closed loop is kept unchanged. In addition, according to the change of the liquid level of the steam generator, the electric valve 22 is automatically opened, the high-pressure nitrogen in the pressure accumulation tank 21 provides driving force, cooling water is provided for the steam generators 15 and 16, and the liquid level of the steam generators is increased or maintained. The aim of avoiding the startup of the passive core cooling system as much as possible is fulfilled.
In contrast to other inventions, the present invention arranges the heat exchanger in the existing condensation tank 1 of the passive nuclear power plant. In the case of unavailable electric pump, after natural circulation of steam-condensed water is established, decay heat can be led out in a passive mode. In addition, the natural circulation is slow to establish, and when the natural circulation is established, the liquid level of the steam generator is probably reduced to a certain setting value, the passive core cooling system is automatically started, and the aim of avoiding the start of the passive core cooling system cannot be achieved. To solve this problem, a pressure accumulator tank 25 is also provided in this patent application, which provides a short supply of water to the steam generator before the natural circulation of steam-condensate is established, using compressed nitrogen.

Claims (2)

1. A steam generator passive water replenishing system for a passive nuclear power plant comprises a starting water supply system, wherein the starting water supply system comprises two starting water supply pumps, the two starting water supply pumps suck water from a condensation water tank, respectively flow through corresponding check valves and isolation valves and then are collected to a starting water supply main pipe, and then respectively flow through corresponding starting water supply regulating valves, starting water supply check valves and starting water supply isolation valves to supply water to two steam generators; the system is characterized by further comprising a steam generator passive water replenishing system on the basis of starting a water supply system, wherein the steam generator passive water replenishing system comprises a heat exchanger and a pressure accumulation box, the heat exchanger is arranged in a condensation water tank, the bottom elevation of the condensation water tank is higher than the top elevation of the steam generator, a steam pipeline at the inlet of the heat exchanger is connected with a steam generator and a main steam pipeline, and an outlet pipeline of the steam generator is connected with a starting water supply main pipe; a certain amount of cooling water is stored in the pressure accumulation box, high-pressure nitrogen is arranged in the pressure accumulation box to maintain pressure, and the outlet of the pressure accumulation box is connected to a starting water supply main pipe through an electric valve.
2. The steam generator passive water replenishment system for a passive nuclear power plant according to claim 1 wherein a pneumatic valve is provided on the heat exchanger outlet line.
CN202011299269.6A 2020-11-19 2020-11-19 Passive water replenishing system of steam generator for passive nuclear power plant Pending CN112289472A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011299269.6A CN112289472A (en) 2020-11-19 2020-11-19 Passive water replenishing system of steam generator for passive nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011299269.6A CN112289472A (en) 2020-11-19 2020-11-19 Passive water replenishing system of steam generator for passive nuclear power plant

Publications (1)

Publication Number Publication Date
CN112289472A true CN112289472A (en) 2021-01-29

Family

ID=74398673

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011299269.6A Pending CN112289472A (en) 2020-11-19 2020-11-19 Passive water replenishing system of steam generator for passive nuclear power plant

Country Status (1)

Country Link
CN (1) CN112289472A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114060784A (en) * 2021-12-13 2022-02-18 中国核动力研究设计院 Water supply system applied to direct-current steam generation device
WO2022233141A1 (en) * 2021-05-07 2022-11-10 苏州热工研究院有限公司 Passive special safety system and water supply system for nuclear power plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2022233141A1 (en) * 2021-05-07 2022-11-10 苏州热工研究院有限公司 Passive special safety system and water supply system for nuclear power plant
CN114060784A (en) * 2021-12-13 2022-02-18 中国核动力研究设计院 Water supply system applied to direct-current steam generation device

Similar Documents

Publication Publication Date Title
KR101389276B1 (en) Passive Safety System of Integral Reactor
US10950358B2 (en) PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
US8559583B1 (en) Passive cooling and depressurization system and pressurized water nuclear power plant
JP5016066B2 (en) Nuclear power plants using nanoparticles in emergency systems and related methods
CN1197092C (en) BWR nuclear power generator
KR101242746B1 (en) Integrated passive safety system outside containment for nuclear power plants
CN104520939A (en) Small modular reactor safety systems
CN101720488B (en) Nuclear power plant using nanoparticles in closed circuits of emergency systems and related method
CN102867548A (en) Active and passive combined secondary side reactor core heat derivation device
CZ283278B6 (en) Pressurized-water reactor
US20130301782A1 (en) Defense in depth safety paradigm for nuclear reactor
KR20140054266A (en) Backup nuclear reactor auxiliary power using decay heat
CN102903402A (en) Advanced secondary side core heat lead-out device
CN112289472A (en) Passive water replenishing system of steam generator for passive nuclear power plant
US20130272473A1 (en) Auxiliary condenser system for decay heat removal in a nuclear reactor
CN106297915B (en) Passive safety injection system for nuclear power station
KR101463441B1 (en) High concentration boron injection system and safety injection system having the same
EP2549484B1 (en) Nuclear power plant
CN202887750U (en) Advanced secondary side reactor core heat leading-out device
CN206541632U (en) A kind of secondary side residual heat removal system
JP2009053049A (en) Safety system of nuclear power plant
KR102044832B1 (en) Safety injection device and nuclear power plant having the same
KR20060020756A (en) Integral pwr with diverse emergency cooling and method of operating same
CN214175702U (en) Passive water replenishing system of steam generator for passive nuclear power plant
KR101191655B1 (en) Passive refill and recovery system for steam generator

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination