CN104733060A - Passive residual heat removal system of marine nuclear power device - Google Patents
Passive residual heat removal system of marine nuclear power device Download PDFInfo
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- CN104733060A CN104733060A CN201510132511.3A CN201510132511A CN104733060A CN 104733060 A CN104733060 A CN 104733060A CN 201510132511 A CN201510132511 A CN 201510132511A CN 104733060 A CN104733060 A CN 104733060A
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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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
- G21C15/185—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy stored in reactor system
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a passive residual heat removal system of a marine nuclear power device. The passive residual heat removal system comprises a containment and a cooling heat exchanger. The containment is internally provided with a reactor pressure vessel, a loop cool pipe section, a loop heat pipe section, a steam generator, a refueling water tank, a 1# residual heat removal heat exchanger, a 2# residual heat removal heat exchanger and a cooling water pipe bundle; the refueling water tank is arranged at the top of the containment; the reactor pressure vessel and the steam generator are connected with the heat pipe section through the loop cool pipe section; the inlet and the outlet of the 1# residual heat removal heat exchanger are respectively connected with the loop heat pipe section and the loop cool pipe section; a main steam pipeline and a water supply pipeline which are connected with the inlet and the outlet of the 2# residual heat removal heat exchanger are arranged on the steam generator; upper and lower ends of the cooling water pipe bundle are respectively connected with the inlet and the outlet of the cooling heat exchanger. The passive residual heat removal system of the marine nuclear power device is independent from external power, is improved in capability of removing residual heat of reactor core through natural circulation, is improved in safety redundancy, power and operation stability, and guarantees operation safety of nuclear reactor.
Description
Technical field
The present invention relates to the safety installations technical field of reactor, be specifically related to a kind of Heat Discharging System of Chinese of atomic marine plant.
Background technology
In the world today, energy crisis highlights day by day, environment is when going from bad to worse, and the utilization of nuclear energy has attracted increasing concern.Because the energy density of nuclear fuel is high, and nuclear power unit operation characteristic is easy to control, generated output is large, and atomic-powered ship has advantageous advantage compared to boats and ships powered by conventional energy.The U.S., Russia, China, Japan and other countries are all greatly developing atomic-powered ship, and in order to avoid the generation of similar Chernobyl nuclear accident, Fukushima nuclear accident, the safety of atomic marine plant becomes the most important thing.
After nuclear reactor shutdown, the fission fragment that heap in-core generates by fissioning and their decay thing still can produce larger afterpower in radioactive decay process, there is sensible heat in primary Ioops cooling medium and equipment simultaneously, also heat can be released during main pump running, if these heats are derived not in time, likely core meltdown can be caused, harm nuclear reactor security of operation.Therefore, atomic marine plant is all equipped with residual heat removal system to derive this part heat.
At present, what be applied to atomic marine plant is energy dynamic formula residual heat removal system mostly, and its compact conformation, power are strong, working stability, but once there is the full ship loss of power accident, all active equipment can not work, and the safety of reactor cannot be protected.And the thermal drivers pressure head that Heat Discharging System of Chinese is formed by the density difference of hot and cold working medium provides driving force, utilize Natural Circulation to derive reactor-loop waste heat, still can stably work when external power is unable to supply.Because atomic-powered ship needs in the face of complicated ocean condition, and isolated in ocean, there is no external power supply, in order to avoid there is nuclear leakage accident, designing a kind of safe and reliable Heat Discharging System of Chinese and being extremely necessary.
There is following two problems in the Heat Discharging System of Chinese that the AP1000 nuclear power technology being now applied to nuclear power plant adopts, one is that Safety Redundancy is low, Residual heat removal heat interchanger is only connected with primary Ioops, after Main Coolant pump shutdown, natural circulation flow is limited, and therefore the speed of Residual heat removal be restricted; Two is do not take heat out of containment, and after absorbing the heat that Residual heat removal heat interchanger brings, the water in material-changing water tank is directly evaporated to containment space, adds the difficulty of the pressure and temperature control in containment.
Summary of the invention
Goal of the invention: the invention provides a kind of employing two being applicable to atomic marine plant and work with the Residual heat removal Natural Circulation that the hot and cold working medium post method of double differences is driving force simultaneously, and heat discharged to sea, still for a long time, stably can derive the Heat Discharging System of Chinese of residual heat of nuclear core when there is the full ship loss of power accident the most at last.
Technical scheme: for solving the problems of the technologies described above, the present invention adopts following technical scheme:
A Heat Discharging System of Chinese for atomic marine plant, comprises the containment be arranged in hull and the cooling heat exchanger be located at outside hull; Be provided with reactor pressure vessel, primary Ioops cold leg, primary Ioops heat pipe section, steam generator, material-changing water tank, 1# Residual heat removal heat interchanger, 2# Residual heat removal heat interchanger in described containment and be located at the chilled water tube bank in material-changing water tank; Described material-changing water tank is opening box body structure, is located at containment headroom, is provided with deionization chilled water in casing, and 1# Residual heat removal heat interchanger and 2# Residual heat removal heat interchanger are all located at material-changing water tank sidewall; The import and export of described reactor pressure vessel is connected with steam generator with heat pipe section respectively by primary Ioops cold leg; The import and export of 1# Residual heat removal heat interchanger is connected with primary Ioops cold leg with primary Ioops heat pipe section respectively; Steam generator top is provided with major steam line, and sidewall is provided with supply line; The import and export of 2# Residual heat removal heat interchanger is connected to secondary circuit tedge, secondary circuit downtake, and secondary circuit tedge is connected with major steam line, supply line respectively with secondary circuit downtake; What chilled water was restrained goes out, import is connected with cooling heat exchanger import and export respectively; The tube bank of 1# Residual heat removal heat interchanger, 2# Residual heat removal heat interchanger and chilled water is all positioned at below material-changing water tank liquid level, the center line horizontal level that the center line horizontal level of cooling heat exchanger is restrained higher than chilled water.
Described primary Ioops cold leg is provided with main coolant pump, can provide circulation power for residual heat removal system.
The center line horizontal level of primary side of steam generator, higher than the center line horizontal level of reactor pressure vessel, can make primary Ioops cooling medium set up Natural Circulation under the effect of the two side column method of double differences.
The secondary circuit downtake of described 2# Residual heat removal heat interchanger is also provided with the bypass of residual heat removal pump and residual heat removal pump, bypass is provided with isolation valve, the condensate water of 2# Residual heat removal heat interchanger all flows back to steam generator by supply line by residual heat removal pump or bypass, when external power is available, isolation valve in pump bypass cuts out, this pump can provide power for the Residual heat removal circulation of secondary circuit, increases circular flow, accelerates the speed of Residual heat removal.
Also water supply tank is provided with in described containment, bottom water supply tank, water delivering orifice is connected with supply line, the height of water supply tank water level is suitable with steam generator normal water level height, when the height of steam generator normal water level lower than water supply tank water level, water supply tank is supplied water to steam generator by water-supply line.
Be provided with reverse checkvalve between described water supply tank and supply line, aqueous reflux covering water tank in steam generator can be prevented.
Preferably, between the entrance of described primary Ioops heat pipe section and 1# Residual heat removal heat interchanger, between primary Ioops cold leg and the outlet of 1# Residual heat removal heat interchanger, on supply line, between supply line and water supply tank, between major steam line and secondary circuit tedge, between the chilled water upper end of restraining and cooling heat exchanger import, the chilled water lower end of restraining and cooling heat exchanger be equipped with isolation valve between exporting.
Principle of work: the thermal drivers pressure head that the Heat Discharging System of Chinese of atomic marine plant of the present invention is formed with the density difference of hot and cold working medium is for power, when there is the full ship loss of power accident, system still can be run for a long time, stably, the waste heat of reactor is exported to final low-temperature receiver---sea, ensures the security of operation of reactor.The primary Ioops heat pipe section of reactor pressure vessel is connected with the import of 1# Residual heat removal heat interchanger, and primary Ioops cold leg is connected with the outlet of 1# Residual heat removal heat interchanger, forms the circulation of first via Residual heat removal; The import and export of 2# Residual heat removal heat interchanger is connected with supply line respectively at the main steam line of steam generator, and steam flows back to steam generator secondary side after heat interchanger condensation, forms the second road Residual heat removal circulation; The chilled water tube bank being arranged in below material-changing water tank liquid level is connected with the cooling heat exchanger be placed in outside hull, forms the 3rd road Residual heat removal circulation; When auxiliary feedwater is unavailable, water supply tank can supply water from trend steam generator, prevents steam generator water level from declining and causes U heat exchange in steam generator exposed, add the security that steam generator runs.
Above-mentioned first via Residual heat removal circulation is positioned at primary Ioops, and the second road Residual heat removal circulation is positioned at secondary circuit.
The NM technology of the present invention is prior art.
Beneficial effect: the Heat Discharging System of Chinese of atomic marine plant of the present invention does not rely on external power, make full use of Natural Circulation, the thermal drivers pressure head formed with the density difference of hot and cold working medium is for driving force, stably derive waste heat in reactor pressure vessel, ensure the security of operation of nuclear reactor; Be provided with Residual heat removal Natural Circulation at primary Ioops and secondary circuit simultaneously, not only improve the ability that system discharges residual heat of nuclear core, and add the Safety Redundancy of system; The heat conduction that material-changing water tank in containment absorbs by cooling heat exchanger is to final low-temperature receiver---sea, reduce the pressure that in material-changing water tank, evaporation of water brings to the pressure and temperature control in containment, make system continuous firing can discharge waste heat in reactor pressure vessel for a long time after shutdown; The residual heat removal pump being arranged on the second road Residual heat removal circulation brings certain dynamic role to system, adds the power of system and the stability of operation.
Accompanying drawing explanation
Fig. 1 is atomic marine plant Heat Discharging System of Chinese structural representation of the present invention;
In figure, 1 is reactor pressure vessel, 2 is main coolant pump, 3 is steam generator, 4 is material-changing water tank, 5 is 1# Residual heat removal heat interchanger, 6 is 2# Residual heat removal heat interchanger, 7 is chilled water tube bank, 8 is cooling heat exchanger, 9 is water supply tank, 10 is residual heat removal pump, 11 is containment, 12 is bypass, 13 is primary Ioops cold leg, 14 is primary Ioops heat pipe section, 15 is major steam line, 16 is supply line, 17 is secondary circuit tedge, 18 is secondary circuit downtake, 19 is isolation valve, 20 is reverse checkvalve, A is the center line horizontal level of reactor pressure vessel, B is the center line horizontal level of primary side of steam generator, C is the height of water supply tank water level, D is steam generator normal water level height, E is the center line horizontal level of cooling heat exchanger, F is the center line horizontal level of chilled water tube bank.
Embodiment
In order to understand the present invention better, illustrate content of the present invention further below in conjunction with embodiment, but content of the present invention is not only confined to the following examples.
Embodiment 1
As shown in Figure 1, a kind of Heat Discharging System of Chinese of atomic marine plant, comprises the containment 11 be arranged in hull and the cooling heat exchanger 8 be located at outside hull; Be provided with reactor pressure vessel 1, primary Ioops cold leg 13, primary Ioops heat pipe section 14, steam generator 3, material-changing water tank 4,1# Residual heat removal heat interchanger 5,2# Residual heat removal heat interchanger 6 in described containment 11 and be located at the chilled water tube bank 7 in material-changing water tank 4; Described material-changing water tank 4 is opening box body structure, is located at containment 11 headroom, is provided with deionization chilled water in casing, and 1# Residual heat removal heat interchanger 5 and 2# Residual heat removal heat interchanger 6 are all located at material-changing water tank 4 sidewall; The import and export of described reactor pressure vessel 1 is connected with steam generator 3 with heat pipe section respectively by primary Ioops cold leg 13; The import and export of 1# Residual heat removal heat interchanger 5 is connected with primary Ioops cold leg 13 with primary Ioops heat pipe section 14 respectively; Steam generator 3 top is provided with major steam line 15, and sidewall is provided with supply line 16; The import and export of 2# Residual heat removal heat interchanger 6 is connected to secondary circuit tedge 17, secondary circuit downtake 18, and secondary circuit tedge 17 is connected with major steam line 15, supply line 16 respectively with secondary circuit downtake 18; Chilled water tube bank 7 go out, import are connected with cooling heat exchanger 8 import and export respectively; The tube bank of 1# Residual heat removal heat interchanger 5,2# Residual heat removal heat interchanger 6 and chilled water 7 is all positioned at below material-changing water tank 4 liquid level, the center line horizontal level F that the center line horizontal level E of cooling heat exchanger restrains higher than chilled water; Primary Ioops cold leg 13 is provided with main coolant pump 2; The center line horizontal level B of primary side of steam generator is higher than the center line horizontal level A of reactor pressure vessel; The secondary circuit downtake 18 of 2# Residual heat removal heat interchanger 6 is also provided with the bypass 12 of residual heat removal pump 10 and residual heat removal pump 10, bypass 12 is provided with isolation valve 19; Also be provided with water supply tank 9 in containment 11, bottom water supply tank 9, water delivering orifice is connected with supply line 16, and the height C of water supply tank water level is suitable with steam generator normal water level height D; Reverse checkvalve 20 is provided with between water supply tank 9 and supply line 16; Between the entrance of primary Ioops heat pipe section 14 and 1# Residual heat removal heat interchanger 5, between primary Ioops cold leg 13 and the outlet of 1# Residual heat removal heat interchanger 5, on supply line 16, between supply line 16 and water supply tank 9, between major steam line 15 and secondary circuit tedge 17, chilled water restrains between the upper end of 7 and cooling heat exchanger 8 import, chilled water restrain 7 lower end and cooling heat exchanger 8 export between be equipped with isolation valve 19.
A branch road is drawn from primary Ioops heat pipe section 14, make primary Ioops cooling medium from the water inlet inflow heat exchanger of 1# Residual heat removal heat interchanger 5 upper cover, by the deionized water cooling in material-changing water tank 4 laggard enter the cold leg of main coolant pump 2 upstream, enter reactor pressure vessel 1 with cooling medium main flow and absorb heat, form first via Residual heat removal Natural Circulation thus.The isolation valve 19 often opened is provided with between 1# Residual heat removal heat interchanger 5 upper cover and reactor-loop heat pipe section 14, cooling medium in Tube Sheet of Heat Exchanger is identical with Water in Water Tanks temperature, pressure is suitable with primary Ioops heat pipe section 14 pressure, when system starts, open after steering order received by isolation valve 19 normally closed between 1# Residual heat removal heat interchanger 5 low head and reactor-loop cold leg 13, because 1# Residual heat removal heat interchanger 5 is managed, interior coolant temperature is low, density is large, post is heavy also large, and therefore the circulation of first via Residual heat removal has larger startup flow.But along with hot and cold working medium density difference reduces to cause thermal drivers pressure head to reduce, the ability that primary Ioops waste heat is derived in the circulation of first via Residual heat removal will reduce.
Discharge the ability of residual heat of nuclear core to maintain system, ensure the security of operation that reactor is long-term after shutdown, secondary circuit also needs to set up the Natural Circulation can discharging residual heat of nuclear core.After shutdown, coolant temperature in reactor-loop cold leg 13 is low, density is large, coolant temperature in heat pipe section is high, density is little, and steam generator 3 primary side center line is higher than the center line horizontal level of reactor pressure vessel 1, the cooling medium of primary Ioops establishes Natural Circulation under the effect of the two side column method of double differences.Main steam valve cuts out because of shutdown simultaneously, normally closed isolation valve 19 between the outlet of steam generator 3 secondary side and 2# Residual heat removal heat interchanger 6 entrance and 2# Residual heat removal heat interchanger 6 exports and normally closed isolation valve 19 between steam generator 3 feed-water intake receive system enabled instruction after open, now be full of steam in tedge, water is filled with in most of space and downtake in the pipe of 2# Residual heat removal heat interchanger 6, under the effect of the two side column method of double differences, steam enters heat interchanger by the water inlet being arranged in 2# Residual heat removal heat interchanger 6 upper cover and is cooled, condensate water flows out from the water delivering orifice being arranged in low head, steam generator 3 is flow to through water-supply line, second road Residual heat removal Natural Circulation has just been set up.
Material-changing water tank 4 is placed in containment 11 headroom, water tank is an open containers, under the heat effect of primary Ioops cooling medium and secondary circuit steam, water temperature in water tank raises gradually, come to life after the temperature that reaches capacity, steam affects the pressure and temperature in containment 11 after directly entering containment 11 space, do not accomplish heat to discharge outside containment 11.Can arrange cooling festoon 7 in material-changing water tank 4, chilled water tube bank 7 is connected by connecting pipe with the cooling heat exchanger 8 be arranged in outside hull space, and the working medium of connecting pipe Bottomhole pressure can be water or other media.In the cold working medium of cooling heat exchanger 8 primary side and chilled water tube bank 7 between hot working fluid density difference effect under, chilled water is Natural Circulation in connecting pipe pipe, and the heat in material-changing water tank 4 is exported to ultimate heat sink---sea.
Residual heat removal pump 10 can be arranged between the outlet of 2# Residual heat removal heat interchanger 6 and the feed-water intake of steam generator 3, and bypass 12 pipeline is set for this pump, when external power is available, isolation valve 19 in pump bypass 12 cuts out, this pump can provide power for the Residual heat removal circulation of secondary circuit, increase circular flow, accelerate the speed of Residual heat removal.After stopping transport, pump becomes a resistance piece, and now open bypass 12 isolation valve 19 of pump, condensate water flows to steam generator 3 supply line 16 from bypass 12, reduces the resistance of the second road Residual heat removal circulation.After shutdown, auxiliary feedwater system replaces main feed system to be that steam generator 3 supplies water, when there is full ship loss of power accident auxiliary feedwater system and losing efficacy, water supply tank 9 water compensating valve is opened, water in water supply tank 9 flows under the influence of gravity into steam generator 3, prevents the too low U heat exchange that causes of steam generator 3 water level exposed.
The Heat Discharging System of Chinese of atomic marine plant of the present invention does not rely on external power, make full use of Natural Circulation, the thermal drivers pressure head formed with the density difference of hot and cold working medium, for driving force, is stably derived waste heat in reactor pressure vessel 1, has been ensured the security of operation of nuclear reactor; Be provided with Residual heat removal Natural Circulation at primary Ioops and secondary circuit simultaneously, not only improve the ability that system discharges residual heat of nuclear core, and add the Safety Redundancy of system; The heat conduction that material-changing water tank 4 in containment 11 absorbs by cooling heat exchanger 8 is to final low-temperature receiver---sea, reduce the pressure that in material-changing water tank 4, evaporation of water brings to the pressure and temperature control in containment 11, make system continuous firing can discharge waste heat in reactor pressure vessel 1 for a long time after shutdown; The residual heat removal pump 10 being arranged on the second road Residual heat removal circulation brings certain dynamic role to system, adds the power of system and the stability of operation.
Above-described embodiment is to explanation of the present invention, is not limitation of the invention, anyly all belongs to protection scope of the present invention to the scheme after simple transformation of the present invention.
Claims (7)
1. a Heat Discharging System of Chinese for atomic marine plant, is characterized in that: comprise the containment (11) be arranged in hull and the cooling heat exchanger (8) be located at outside hull; Be provided with reactor pressure vessel (1), primary Ioops cold leg (13), primary Ioops heat pipe section (14), steam generator (3), material-changing water tank (4), 1# Residual heat removal heat interchanger (5), 2# Residual heat removal heat interchanger (6) in described containment (11) and be located at chilled water tube bank (7) in material-changing water tank (4); Described material-changing water tank (4) is opening box body structure, is located at containment (11) headroom, is provided with deionization chilled water in casing, and 1# Residual heat removal heat interchanger (5) and 2# Residual heat removal heat interchanger (6) are all located at material-changing water tank (4) sidewall; The import and export of described reactor pressure vessel (1) is connected with steam generator (3) with heat pipe section respectively by primary Ioops cold leg (13); The import and export of 1# Residual heat removal heat interchanger (5) is connected with primary Ioops cold leg (13) with primary Ioops heat pipe section (14) respectively; Steam generator (3) top is provided with major steam line (15), and sidewall is provided with supply line (16); The import and export of 2# Residual heat removal heat interchanger (6) is connected to secondary circuit tedge (17), secondary circuit downtake (18), and secondary circuit tedge (17) is connected with major steam line (15), supply line (16) respectively with secondary circuit downtake (18); Chilled water tube bank the going out of (7), import are connected with cooling heat exchanger (8) import and export respectively; 1# Residual heat removal heat interchanger (5), 2# Residual heat removal heat interchanger (6) and chilled water tube bank (7) are all positioned at below material-changing water tank (4) liquid level, the center line horizontal level (F) that the center line horizontal level (E) of cooling heat exchanger is restrained higher than chilled water.
2. the Heat Discharging System of Chinese of atomic marine plant as claimed in claim 1, is characterized in that: described primary Ioops cold leg (13) is provided with main coolant pump (2).
3. the Heat Discharging System of Chinese of atomic marine plant as claimed in claim 2, is characterized in that: the center line horizontal level (B) of primary side of steam generator is higher than the center line horizontal level (A) of reactor pressure vessel.
4. the Heat Discharging System of Chinese of atomic marine plant as claimed in claim 1, it is characterized in that: the bypass (12) the secondary circuit downtake (18) of described 2# Residual heat removal heat interchanger (6) being also provided with residual heat removal pump (10) and residual heat removal pump (10), bypass (12) is provided with isolation valve (19).
5. the Heat Discharging System of Chinese of the atomic marine plant as described in claim 1-4 any one, it is characterized in that: in described containment (11), be also provided with water supply tank (9), water supply tank (9) bottom water delivering orifice is connected with supply line (16), and the height (C) of water supply tank water level is suitable with steam generator normal water level height (D).
6. the Heat Discharging System of Chinese of atomic marine plant as claimed in claim 5, is characterized in that: be provided with reverse checkvalve (20) between described water supply tank (9) and supply line (16).
7. the Heat Discharging System of Chinese of atomic marine plant as claimed in claim 6, it is characterized in that: between described primary Ioops heat pipe section (14) and the entrance of 1# Residual heat removal heat interchanger (5), between the outlet of primary Ioops cold leg (13) and 1# Residual heat removal heat interchanger (5), on supply line (16), between supply line (16) and water supply tank (9), between major steam line (15) and secondary circuit tedge (17), between the upper end of chilled water tube bank (7) and cooling heat exchanger (8) import, isolation valve (19) is equipped with between the lower end of chilled water tube bank (7) and cooling heat exchanger (8) export.
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| CN201510132511.3A CN104733060A (en) | 2015-03-25 | 2015-03-25 | Passive residual heat removal system of marine nuclear power device |
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| CN201510132511.3A CN104733060A (en) | 2015-03-25 | 2015-03-25 | Passive residual heat removal system of marine nuclear power device |
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