CN103117101A - Start-stop auxiliary device used in integral reactor and cold starting method of integral reactor - Google Patents

Start-stop auxiliary device used in integral reactor and cold starting method of integral reactor Download PDF

Info

Publication number
CN103117101A
CN103117101A CN2013100202899A CN201310020289A CN103117101A CN 103117101 A CN103117101 A CN 103117101A CN 2013100202899 A CN2013100202899 A CN 2013100202899A CN 201310020289 A CN201310020289 A CN 201310020289A CN 103117101 A CN103117101 A CN 103117101A
Authority
CN
China
Prior art keywords
water
storage tank
water storage
valve
reactor
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.)
Granted
Application number
CN2013100202899A
Other languages
Chinese (zh)
Other versions
CN103117101B (en
Inventor
夏庚磊
彭敏俊
杜雪
余大力
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.)
Harbin Engineering University
Original Assignee
Harbin Engineering University
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 Harbin Engineering University filed Critical Harbin Engineering University
Priority to CN201310020289.9A priority Critical patent/CN103117101B/en
Publication of CN103117101A publication Critical patent/CN103117101A/en
Application granted granted Critical
Publication of CN103117101B publication Critical patent/CN103117101B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • 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 provides a start-stop auxiliary device used in an integral reactor and a cold starting method of the integral reactor. An inlet of a starting separator is connected with an outlet conduit of a once-through steam generator, an outlet of the starting separator is connected with a main steam pipe through a steam valve, and a drain outlet is connected with a water storage tank. An outlet at the bottom of the water storage tank is connected with a circulating water pump, and one conduit at the outlet of the water storage tank is connected with a condenser through an outlet stop valve of the water storage tank, a water storage tank water level control valve and a thermoreduction and dropping device. The circulating water pump is connected with a water supply conduit at the inlet of the once-through steam generator through a circulating water-carrying control valve. A water feed pump is connected with the condenser, the water feed pump is further connected with the inlet conduit of the once-through steam generator through a main water feed valve and with the water storage tank through a cold water valve. The start-stop auxiliary device is capable of increasing the temperature and pressure of refrigerant in a first circuit when the reactor starts, starting pressure and starting flow of a second circuit are established effectively, phenomenon of unstable flow is avoided, working media and heat energy are recycled effectively, and starting time is shortened.

Description

Be used for the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor
Technical field
What the present invention relates to is the start and stop servicing unit of integral reactor.The present invention also relates to a kind of cold start-up method of integral reactor of the start and stop servicing unit with integral reactor.
Background technology
Due to the requirement that the space is arranged, integrated nuclear reactor tends to adopt the once through steam generator of compact efficient.Secondary circuit working medium forces to flow through heating surface, by a circuit cools agent heating, through preheating, evaporation, overheated and produce superheated vapor and deliver to the turbine system acting.Once through steam generator has simple in structure, and maneuverability is good, and the characteristics that heat consumption rate is low are particularly suitable for needing the atomic marine plant of frequent variable load operation.Once through steam generator inside is comprised of a hundreds of parallel port, and the hydrodynamic property curve of each passage is different, exists violent phase transition process during operation in evaporation tube, is easy to produce the diphasic flow wild effect of various ways.In order to guarantee the safe and stable operation of once through steam generator, must guarantee the minimum feedwater flow of once through steam generator.
In the pressurized-water reactor nuclear power plant Cold Start, at first to realize the increasing temperature and pressure process of a circuit cools agent.And the heating rate of a circuit system must be strict controlled in 30-40 ℃/below h, pressure rise can not be too fast.In normal course of operation, the feedwater of once through steam generator is the subcooled water from condenser, in the reactor Cold Start, the cold feedwater of continual mistake can be taken away amount of heat, and the mechanical work of depending merely on voltage stabilizer electrical heating power and main pump can't be completed the increasing temperature and pressure process of a circuit system.And start requirement for satisfying, and must guarantee that the secondary side feedwater all is heated to be superheated vapor, this will have the reactor capability corresponding with feedwater flow after will asking reactor start-up to complete.How to realize the increasing temperature and pressure of a circuit cools agent in start-up course, complete the startup of reactor, and the secondary circuit feedwater is heated to be superheated vapor; How the two-phase mixture that in start-up course, the once through steam generator outlet produces is processed, and is all problem in the urgent need to address.
Summary of the invention
The purpose of this invention is to provide a kind of increasing temperature and pressure that can realize a circuit cools agent in the process that integral reactor starts, avoid the appearance of flowing instability phenomenon, and effectively reclaim working medium and heat, shorten the start and stop servicing unit that is used for integral reactor of reactor start-up time.The present invention also aims to provide a kind of cold start-up method of the integral reactor based on the start and stop servicing unit for integral reactor of the present invention.
The object of the present invention is achieved like this:
Start and stop servicing unit for integral reactor of the present invention comprises startup separation vessel 15, water storage tank 16 and water circulating pump 17; The import that starts separation vessel 15 is connected with the outlet conduit of once through steam generator 4, and the steam (vapor) outlet that starts separation vessel 15 is connected with main steam line through steam valve 20, and the hydrophobic outlet that starts separation vessel 15 is connected with water storage tank 16; The outlet at bottom of water storage tank 16 is connected with water circulating pump 17, and water storage tank 16 outlet has one road device for cleaning pipeline to cross water storage tank outlet shutoff valve 25, water storage tank level control valve 26 and desuperheat dropping equipment 27 to be connected with condenser 22; Water circulating pump 17 is connected with once through steam generator 4 import feedwater pipings by circulating water flow control valve 18; Feed pump 23 is connected with condenser 22, also is connected with once through steam generator 4 inlet pipelines, is connected with water storage tank 16 by cold valves 28 by main feed valve 24; Circulating water flow control valve 18 is connected with the steam generator feed water control system with main feed valve 24; Water storage tank level control valve 26, steam valve 20 and cold valves 28 are connected with the water storage tank control pressurer system.
Start and stop servicing unit for integral reactor of the present invention can also comprise:
1, water circulating pump 17 outlet also has one road device for cleaning pipeline to cross recirculation water flowrate control valve 19 to be connected with water storage tank 16, and recirculation water flowrate control valve 19 is connected with the steam generator feed water control system.
2, described startup separation vessel 15 is external steam-water separator, is used in start-up course vapour, gas-liquid two-phase liquid are separated, start complete after, the switching by flowrate control valve 28 and flowrate control valve 29 will start separation vessel and withdraw from secondary coolant circuit system.
3, described water circulating pump 17 is power-actuated water pump, and pump rotary speed opens at reactor, remain constant in stopping process, is used at once through steam generator 4, starts between separation vessel 15 and water storage tank 16 and set up stable circulating water flow.
Cold start-up method based on the integral reactor of the start and stop servicing unit for integral reactor of the present invention comprises the following steps:
(1) after the exhaust of reactor water-filling was completed, reactor was in full water state, opened the voltage stabilizer shower valve, used the power of voltage stabilizer electric heating part 9 and the mechanical work of main pump 3 to improve a circuit cools agent temperature;
In the time of (2) one circuit system increasing temperature and pressure, start and stop backup system water storage tank control pressurer system action regulating tank pressure meets the demands, water circulating pump 17 is opened, recirculated water enters once through steam generator 4 by water storage tank 16 through circulating water flow control valve 18, flowed back to water storage tank 16 after one circuit cools agent heating, completed once circulation;
(3) after voltage stabilizer 7 temperature meet the demands, set up voltage stabilizer 7 vapour chambeies by 11 drainings of letdown flow operation valve, then utilize the power of voltage stabilizer electric heating part 9 to improve voltage stabilizer 7 pressure to specified operating pressure;
(4) adjustment reactor power control system 12 realization responses heaps are critical, promote reactor 1 power, realize the core heat temperature raising, and along with the raising of reactor capability, secondary circuit recirculated water produces boiling gradually;
(5) along with the lifting of reactor capability, the steam generator feed water control system is constantly adjusted the aperture of recirculation flow control valve 19, circulating water flow control valve 18 and main feed valve 24, guarantees that once through steam generator import feedwater flow is stable.
The invention provides a kind of start and stop backup system that is equipped with the integral reactor of water circulating pump, this system can realize the increasing temperature and pressure of a circuit cools agent in the process that integral reactor starts, complete the startup of reactor; Effectively set up the secondary circuit starting pressure and start flow, avoiding the appearance of flowing instability phenomenon, and effectively reclaim working medium and heat, shortening the reactor start-up time.
The invention has the beneficial effects as follows, the increasing temperature and pressure of a circuit cools agent in the reactor Cold Start and the safe and stable operation of once through steam generator have been realized, can reclaim most of working medium and heat, use the core-mode of electricity united heating heat greatly to shorten the time of reactor start-up.
Description of drawings
Fig. 1 is the structural representation of the start and stop servicing unit for integral reactor of the present invention.
Fig. 2 integral reactor start-up course curve map.
Embodiment
For example the present invention is done more detailed description below in conjunction with accompanying drawing:
In conjunction with Fig. 1, the import that starts separation vessel 15 is connected with the outlet conduit of once through steam generator 4; The steam (vapor) outlet that starts separation vessel 15 is connected with main steam line through steam valve 20; The hydrophobic outlet that starts separation vessel 15 is connected with water storage tank 16; The outlet at bottom of water storage tank 16 is connected with water circulating pump 17; Water circulating pump 17 is connected with once through steam generator 4 import feedwater pipings by circulating water flow control valve 18; Water circulating pump 17 outlet also has one road device for cleaning pipeline to cross recirculation water flowrate control valve 19 to be connected with water storage tank 16; Water storage tank 16 outlet has one road device for cleaning pipeline to cross water storage tank outlet shutoff valve 25, water storage tank level control valve 26 and desuperheat dropping equipment 27 to be connected with condenser 22; Feed pump 23 is connected with the secondary circuit condensate system, and is connected with once through steam generator 4 inlet pipelines by main feed valve 24; Circulating water flow control valve 18, recirculation flow control valve 19 and main feed valve 24 are connected with the steam generator feed water control system; Water storage tank level control valve 26, steam valve 20 and cold valves 28 are connected with the water storage tank control pressurer system.Described startup separation vessel 15 is external steam-water separator, is used in start-up course vapour, gas-liquid two-phase liquid are separated, start complete after, the switching by flowrate control valve 28 and flowrate control valve 29 will start separation vessel and withdraw from secondary coolant circuit system.Described water circulating pump 17 is power-actuated water pump, it is characterized in that pump rotary speed opens at reactor, remains constant in stopping process, is used at once through steam generator 4, starts between separation vessel 15 and water storage tank 16 and set up stable circulating water flow.Described recirculation water flowrate control valve 19 is used for the low liquid level of water storage tank 16 to be controlled, and during lower than setting value, by regulating the aperture of recirculation water flowrate control valve 19, a part of recirculated water is returned water tank 16 again when water storage tank 16 water levels, prevents that water tank is evacuated.Described steam generator feed water control system guarantees that according to the flow regulation circulating water flow control valve 18 of recirculation water and the aperture of main feed valve 24 steam generator import feedwater flow remains constant.Described water storage tank control pressurer system be used for to be regulated the pressure of water storage tank 16, and during lower than restriction, cold valves 28 is opened water tank is squeezed in part feedwater, improves pressure when pressure; During higher than limit value, water storage tank level control valve 26 or steam valve 20 are opened, and reduce tank pressure by draining and steam discharge respectively when pressure.
Representing the Cold Start of integral reactor in the curve map of Fig. 2 by important parameter, is procedure parameter and the relation of time in the integral reactor start-up course of determining by simulator program.Be in full water state after the exhaust of reactor water-filling is completed, voltage stabilizer does not have the pressure control ability.At first open voltage stabilizer shower valve 8, start main pump 3 high-speed cruisings, drop into voltage stabilizer electrical heating elements 9, utilize the mechanical work of the power of voltage stabilizer electric heating part and main pump to carry out heat temperature raising to a loop Main Coolant and boost.Along with the rising of a circuit cools agent temperature, a Loop Water volumetric expansion, pressure raises, and needs to be interrupted to open letdown flow operation valve 11 and carry out draining, makes within a circuit pressure remains on prescribed limits.
In one circuit cools agent increasing temperature and pressure process, be full of water in the start and stop backup system, pressure is controlled by water storage tank altitude valve 26 and cold valves 28.Start the feedwater flow operation of water circulating pump maintenance 15%.The hot water of steam generator outlet enters water storage tank 16 through steam-water separator 15, then is recycled water pump 17 and again squeezes into steam generator 4, forms a circulation.During lower than 233.0 ℃ (saturation temperature that 3.0MPa pressure is corresponding), start and stop backup system water temperature inside and a circuit cools agent temperature are almost identical in a circuit cools agent temperature.Because circulating water temperature rising volumetric expansion, water storage tank control pressurer system are regulated water storage tank altitude valve 26 and carried out draining, prevent the water storage tank superpressure.Draining enters condenser 22 after 27 step-downs of desuperheat reducing transformer.
When a circuit cools agent temperature reaches 210 ℃, close voltage stabilizer shower valve 8, improve the power of voltage stabilizer electric heating part 9, widen gradually the temperature difference between voltage stabilizer 8 and a circuit cools agent.When the voltage stabilizer temperature reaches 240 ℃, close voltage stabilizer electric heating part 9, open 11 drainings of letdown flow operation valve, set up the voltage stabilizer air cavity.Then open the steam water interface in voltage stabilizer electric heating part 9 heating voltage stabilizers 8, make the voltage stabilizer pressure rise to specified operating pressure.Need in the process of boosting to be interrupted and open 11 drainings of letdown flow operation valve, guarantee the voltage stabilizer water level.
After one circuit cools agent pressure met the demands, conditioned reaction heap power control system 12 made reactor critical, and promoted gradually reactor capability and carry out the core heat temperature raising.One circuit cools agent temperature is during lower than saturation temperature corresponding to 3.0MPa pressure, and secondary circuit recirculated water is single-phase state, stablizes the water tank internal pressure by the draining of water storage tank altitude valve 26; Along with the lasting increase of reactor capability, a circuit cools agent temperature raises rapidly.Recirculated water in the start and stop backup system is heated to state of saturation gradually, when steam generator 4 outlets produce two-phase mixture, 15 pairs of two-phase fluids of steam-water separator separate, saturated vapour gathers at the steam-water separator top, be steady pressure, the continuous draining of water storage tank altitude valve 26 makes steam-water separator 15 water level inside constantly descend, after water level meets the demands, can open main steam valve 20 and carry out exhaust, guarantee the pressure of steam-water separator 15 by the aperture of regulating main steam valve 20.
Along with the increase of reactor capability, steam production constantly raises, and the saturation water flow that enters water storage tank 16 reduces, cause the interior water level of water storage tank 16 to descend, open recirculation flow control valve 19 this moment, makes a part of recirculated water again flow into water tank 16, prevents that water tank is evacuated.Steam generator feedwater flow control system adjusting circulating water flow control valve 18 and main feed valve 24 cooperatively interact simultaneously, utilize main feedwater to come reducing of compensation cycle discharge, guarantee that once through steam generator import feedwater flow remains unchanged.Along with the rising of reactor capability, main feedwater flow constantly increases, and circulating water flow reduces gradually, until the steam generator feedwater is all given by main feedwater, and the whole recirculation flow recovery tanks 16 of recirculated water, the steam generator feedwater all is produced as superheated vapor.Can close circulating water flow control valve 18 and water circulating pump 17, switch flowrate control valve 28 and flowrate control valve 29 the start and stop backup system is withdrawed from, start-up course is completed.In start-up course, the temperature of once through steam generator import feedwater is elevated near state of saturation by subcooled water and then is transitioned into again supercooled state.

Claims (6)

1. a start and stop servicing unit that is used for integral reactor, is characterized in that: comprise starting separation vessel (15), water storage tank (16) and water circulating pump (17); The import that starts separation vessel (15) is connected with the outlet conduit of once through steam generator (4), the steam (vapor) outlet that starts separation vessel (15) is connected with main steam line through steam valve (20), and the hydrophobic outlet that starts separation vessel (15) is connected with water storage tank (16); The outlet at bottom of water storage tank (16) is connected with water circulating pump (17), and water storage tank (16) outlet has one road device for cleaning pipeline to cross water storage tank outlet shutoff valve (25), water storage tank level control valve (26) and desuperheat dropping equipment (27) to be connected with condenser (22); Water circulating pump (17) is connected with once through steam generator (4) import feedwater piping by circulating water flow control valve (18); Feed pump (23) is connected with condenser (22), also is connected with once through steam generator (4) inlet pipeline, is connected with water storage tank (16) by cold valves (28) by main feed valve (24); Circulating water flow control valve (18) is connected with the steam generator feed water control system with main feed valve (24); Water storage tank level control valve (26), steam valve (20) and cold valves (28) are connected with the water storage tank control pressurer system.
2. the start and stop servicing unit for integral reactor according to claim 1, it is characterized in that: water circulating pump (17) outlet also has one road device for cleaning pipeline to cross recirculation water flowrate control valve (19) to be connected with water storage tank (16), and recirculation water flowrate control valve (19) is connected with the steam generator feed water control system.
3. the start and stop servicing unit for integral reactor according to claim 1 and 2, it is characterized in that: described startup separation vessel (15) is external steam-water separator, be used in start-up course vapour, gas-liquid two-phase liquid are separated, start complete after, the switching by flowrate control valve (28) and flowrate control valve (29) will start separation vessel and withdraw from secondary coolant circuit system.
4. the start and stop servicing unit for integral reactor according to claim 1 and 2, it is characterized in that: described water circulating pump (17) is power-actuated water pump, pump rotary speed opens at reactor, remain constant in stopping process, is used at once through steam generator (4), starts between separation vessel (15) and water storage tank (16) and set up stable circulating water flow.
5. the start and stop servicing unit for integral reactor according to claim 3, it is characterized in that: described water circulating pump (17) is power-actuated water pump, pump rotary speed opens at reactor, remain constant in stopping process, is used at once through steam generator (4), starts between separation vessel (15) and water storage tank (16) and set up stable circulating water flow.
6. cold start-up method based on the integral reactor of the described start and stop servicing unit for integral reactor of claim 1 is characterized in that:
(1) after the exhaust of reactor water-filling was completed, reactor was in full water state, opened the voltage stabilizer shower valve, used the power of voltage stabilizer electric heating part (9) and the mechanical work of main pump (3) to improve a circuit cools agent temperature;
In the time of (2) one circuit system increasing temperature and pressure, start and stop backup system water storage tank control pressurer system action regulating tank pressure meets the demands, water circulating pump (17) is opened, recirculated water enters once through steam generator (4) by water storage tank (16) through circulating water flow control valve (18), flowed back to water storage tank (16) after one circuit cools agent heating, completed once circulation;
(3) after voltage stabilizer (7) temperature meets the demands, set up voltage stabilizer (7) vapour chamber by letdown flow operation valve (11) draining, then utilize the power of voltage stabilizer electric heating part (9) to improve voltage stabilizer (7) pressure to specified operating pressure;
(4) adjustment reactor power control system (12) realization response heap is critical, promotes reactor (1) power, realizes the core heat temperature raising, and along with the raising of reactor capability, secondary circuit recirculated water produces boiling gradually;
(5) along with the lifting of reactor capability, the steam generator feed water control system is constantly adjusted the aperture of recirculation flow control valve (19), circulating water flow control valve (18) and main feed valve (24), guarantees that once through steam generator import feedwater flow is stable.
CN201310020289.9A 2013-01-19 2013-01-19 For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor Active CN103117101B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201310020289.9A CN103117101B (en) 2013-01-19 2013-01-19 For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201310020289.9A CN103117101B (en) 2013-01-19 2013-01-19 For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor

Publications (2)

Publication Number Publication Date
CN103117101A true CN103117101A (en) 2013-05-22
CN103117101B CN103117101B (en) 2015-09-30

Family

ID=48415450

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201310020289.9A Active CN103117101B (en) 2013-01-19 2013-01-19 For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor

Country Status (1)

Country Link
CN (1) CN103117101B (en)

Cited By (23)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105118532A (en) * 2015-09-11 2015-12-02 中广核(北京)仿真技术有限公司 Integrated reactor
CN105605548A (en) * 2016-03-25 2016-05-25 上海核工程研究设计院 Steam generator with external steam-water separator
CN106782720A (en) * 2017-02-28 2017-05-31 西安热工研究院有限公司 A kind of utilization auxiliary steam heating and the system and method for cooling start and stop heaping equipment
CN106981322A (en) * 2017-04-26 2017-07-25 西安热工研究院有限公司 A kind of system and method for being used to verify HTGR start and stop heaping equipment function
CN107194103A (en) * 2017-06-07 2017-09-22 哈尔滨工程大学 A kind of nuclear facilities model radiation field dosage emulation mode based on 3dsMax
CN107437436A (en) * 2017-07-28 2017-12-05 中国核动力研究设计院 The secondary circuit energy expenditure simulation test device and method of power adjusting can be carried out
CN108278590A (en) * 2018-03-14 2018-07-13 西安热工研究院有限公司 A kind of system and method for HTGR Nuclear Power Plant Cooling at reactor shutdown
CN109613429A (en) * 2018-12-17 2019-04-12 广西电网有限责任公司电力科学研究院 A kind of PWR steam generator model time constant test macro and method
CN110186026A (en) * 2019-05-06 2019-08-30 中广核研究院有限公司 The dry type hot starting, hot start method of continuous steam generator
CN110534213A (en) * 2019-09-04 2019-12-03 哈尔滨工程大学 A kind of cooling fuel combination reactor system of heat pipe
CN110542325A (en) * 2019-09-26 2019-12-06 岭澳核电有限公司 Condenser vacuum system of nuclear power station
CN110634580A (en) * 2019-09-26 2019-12-31 哈尔滨工程大学 Heat pipe type deep sea application nuclear reactor system
CN110767332A (en) * 2019-10-14 2020-02-07 哈尔滨工程大学 Passive residual heat removal system for high-temperature heat pipe reactor
CN111023072A (en) * 2019-12-18 2020-04-17 中广核研究院有限公司 Two return circuits of straight-flow steam generator open and stop system
CN111174191A (en) * 2020-01-02 2020-05-19 中国核电工程有限公司 Reactor start-stop system and method
CN111540488A (en) * 2020-05-15 2020-08-14 哈尔滨工程大学 Flow mixing device arranged at descending section of integrated reactor pressure vessel
CN111933317A (en) * 2020-07-01 2020-11-13 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Device and method for detecting thermal state performance of control rod driving mechanism
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
CN113488207A (en) * 2021-06-18 2021-10-08 中广核研究院有限公司 Reactor starting method and system
CN113539527A (en) * 2021-06-16 2021-10-22 西安交通大学 Method and system for adjusting startup of space heat pipe cooling reactor
CN114856726A (en) * 2022-05-20 2022-08-05 上海交通大学 Method for determining exhaust steam volume flow and humidity of saturated steam turbine in real time
WO2022166186A1 (en) * 2021-02-07 2022-08-11 西安热工研究院有限公司 Once-through steam generating system and method with intermediate steam and water separation
CN115050491A (en) * 2022-06-24 2022-09-13 中国核动力研究设计院 Full-pressure type auxiliary heating and boosting system and method for small modular reactor

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109404071B (en) * 2018-12-17 2021-04-13 广西电网有限责任公司电力科学研究院 Identification method for pressurized water reactor steam generator model time constant

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6021493A (en) * 1983-07-15 1985-02-02 株式会社日立製作所 Automatic output regulator for reactor
JPS63196896A (en) * 1987-02-12 1988-08-15 株式会社東芝 Nuclear reactor output controller
CN102081059A (en) * 2010-11-25 2011-06-01 哈尔滨工程大学 Forced-convection heat transfer experimental device for strong inner heat source containing porous medium passage

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6021493A (en) * 1983-07-15 1985-02-02 株式会社日立製作所 Automatic output regulator for reactor
JPS63196896A (en) * 1987-02-12 1988-08-15 株式会社東芝 Nuclear reactor output controller
CN102081059A (en) * 2010-11-25 2011-06-01 哈尔滨工程大学 Forced-convection heat transfer experimental device for strong inner heat source containing porous medium passage

Cited By (37)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105118532A (en) * 2015-09-11 2015-12-02 中广核(北京)仿真技术有限公司 Integrated reactor
CN105605548A (en) * 2016-03-25 2016-05-25 上海核工程研究设计院 Steam generator with external steam-water separator
CN106782720A (en) * 2017-02-28 2017-05-31 西安热工研究院有限公司 A kind of utilization auxiliary steam heating and the system and method for cooling start and stop heaping equipment
CN106981322A (en) * 2017-04-26 2017-07-25 西安热工研究院有限公司 A kind of system and method for being used to verify HTGR start and stop heaping equipment function
CN106981322B (en) * 2017-04-26 2018-10-23 西安热工研究院有限公司 A kind of system and method for verifying high temperature gas cooled reactor start and stop heaping equipment function
CN107194103B (en) * 2017-06-07 2020-11-10 哈尔滨工程大学 Nuclear facility model radiation field dose simulation method based on 3dsMax
CN107194103A (en) * 2017-06-07 2017-09-22 哈尔滨工程大学 A kind of nuclear facilities model radiation field dosage emulation mode based on 3dsMax
CN107437436A (en) * 2017-07-28 2017-12-05 中国核动力研究设计院 The secondary circuit energy expenditure simulation test device and method of power adjusting can be carried out
CN107437436B (en) * 2017-07-28 2019-02-22 中国核动力研究设计院 It is able to carry out the secondary circuit energy consumption simulation test device and method of power regulation
CN108278590A (en) * 2018-03-14 2018-07-13 西安热工研究院有限公司 A kind of system and method for HTGR Nuclear Power Plant Cooling at reactor shutdown
CN108278590B (en) * 2018-03-14 2023-08-01 西安热工研究院有限公司 System and method for shutdown cooling of high-temperature gas cooled reactor nuclear power plant
CN109613429A (en) * 2018-12-17 2019-04-12 广西电网有限责任公司电力科学研究院 A kind of PWR steam generator model time constant test macro and method
CN109613429B (en) * 2018-12-17 2021-01-05 广西电网有限责任公司电力科学研究院 Pressurized water reactor steam generator model time constant testing system and method
CN110186026A (en) * 2019-05-06 2019-08-30 中广核研究院有限公司 The dry type hot starting, hot start method of continuous steam generator
CN110534213B (en) * 2019-09-04 2022-09-27 哈尔滨工程大学 Heat pipe cooling mixed fuel reactor system
CN110534213A (en) * 2019-09-04 2019-12-03 哈尔滨工程大学 A kind of cooling fuel combination reactor system of heat pipe
CN110542325A (en) * 2019-09-26 2019-12-06 岭澳核电有限公司 Condenser vacuum system of nuclear power station
CN110634580A (en) * 2019-09-26 2019-12-31 哈尔滨工程大学 Heat pipe type deep sea application nuclear reactor system
CN110634580B (en) * 2019-09-26 2022-05-13 哈尔滨工程大学 Heat pipe type deep sea application nuclear reactor system
CN110542325B (en) * 2019-09-26 2021-03-02 岭澳核电有限公司 Condenser vacuum system of nuclear power station
CN110767332A (en) * 2019-10-14 2020-02-07 哈尔滨工程大学 Passive residual heat removal system for high-temperature heat pipe reactor
CN110767332B (en) * 2019-10-14 2022-07-15 哈尔滨工程大学 Passive residual heat removal system for high-temperature heat pipe reactor
CN111023072A (en) * 2019-12-18 2020-04-17 中广核研究院有限公司 Two return circuits of straight-flow steam generator open and stop system
CN111023072B (en) * 2019-12-18 2022-01-11 中广核研究院有限公司 Two return circuits of straight-flow steam generator open and stop system
CN111174191A (en) * 2020-01-02 2020-05-19 中国核电工程有限公司 Reactor start-stop system and method
CN111174191B (en) * 2020-01-02 2022-03-04 中国核电工程有限公司 Reactor start-stop system and method
CN111540488B (en) * 2020-05-15 2022-04-29 哈尔滨工程大学 Flow mixing device arranged at descending section of integrated reactor pressure vessel
CN111540488A (en) * 2020-05-15 2020-08-14 哈尔滨工程大学 Flow mixing device arranged at descending section of integrated reactor pressure vessel
CN111933317A (en) * 2020-07-01 2020-11-13 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Device and method for detecting thermal state performance of control rod driving mechanism
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
WO2022166186A1 (en) * 2021-02-07 2022-08-11 西安热工研究院有限公司 Once-through steam generating system and method with intermediate steam and water separation
CN113539527A (en) * 2021-06-16 2021-10-22 西安交通大学 Method and system for adjusting startup of space heat pipe cooling reactor
CN113539527B (en) * 2021-06-16 2022-12-09 西安交通大学 Method and system for adjusting startup of space heat pipe cooling reactor
WO2022262225A1 (en) * 2021-06-18 2022-12-22 中广核研究院有限公司 Reactor starting method and system
CN113488207A (en) * 2021-06-18 2021-10-08 中广核研究院有限公司 Reactor starting method and system
CN114856726A (en) * 2022-05-20 2022-08-05 上海交通大学 Method for determining exhaust steam volume flow and humidity of saturated steam turbine in real time
CN115050491A (en) * 2022-06-24 2022-09-13 中国核动力研究设计院 Full-pressure type auxiliary heating and boosting system and method for small modular reactor

Also Published As

Publication number Publication date
CN103117101B (en) 2015-09-30

Similar Documents

Publication Publication Date Title
CN103117101B (en) For the start and stop servicing unit of integral reactor and the cold start-up method of integral reactor
CN102543235B (en) System of controlling steam generator level during main feed-water control valve transfer for nuclear power plant
CN102194535B (en) Pre-service hydrostatic test integrated system on secondary side of steam generator
CN104713074B (en) A kind of direct current cooker starts the hydrophobic System and method for utilizing pressure flash vessel to reclaim
CN108278590B (en) System and method for shutdown cooling of high-temperature gas cooled reactor nuclear power plant
CN204962711U (en) Supercritical unit or super supercritical unit do not have oxygen -eliminating device heat regenerative system
CN102650424B (en) Direct-current furnace starting system matched with middle-pressure flash tank and used for comprehensively recycling working medium and heat
Xia et al. Analysis of natural circulation operational characteristics for integrated pressurized water reactor
CN105402714A (en) Pump-free starting system of supercritical once-through boiler and starting method
CN202188480U (en) Direct-current furnace startup system with media voltage expansion separator
CN105276564A (en) Deaerator-free reheating system of supercritical (ultra-supercritical) unit
Du et al. Operation optimization of auxiliary electric boiler system in HTR-PM nuclear power plant
CN114446503A (en) System of integrated small reactor nuclear power unit and reactor operation method
CN205480937U (en) 300MW and above grade coal -fired power unit's condensate water moisturizing device
CN110726132A (en) Method and system for supplying water to steam generator of nuclear power station under low-power working condition
CN207962612U (en) A kind of system of HTGR Nuclear Power Plant Cooling at reactor shutdown
CN106370690B (en) Pipeline two-phase flow flash evaporation test system and method
CN211071146U (en) Steam generator for cleaning oil pipe
CN205593029U (en) Soda heat transfer initial station is optimized to thermal efficiency
CN205208528U (en) Overcritical once -through boiler does not take pump start -up system
CN106382620A (en) Low-pressure water supply system for steam extraction and backheating of power station unit
CN105605554A (en) Condensation water replenishing method and device for 300MW and above thermal power generator sets
CN205955783U (en) Draw gas low -pressure system of heating boiler feedwater of power station steam turbine
CN217423215U (en) Deoxidizing cooling anti-cavitation water supply system
CN204534539U (en) Boiler water filling system

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant