CN205541975U - Deep well formula ordinary pressure nuclear heating system - Google Patents
Deep well formula ordinary pressure nuclear heating system Download PDFInfo
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- CN205541975U CN205541975U CN201520965887.8U CN201520965887U CN205541975U CN 205541975 U CN205541975 U CN 205541975U CN 201520965887 U CN201520965887 U CN 201520965887U CN 205541975 U CN205541975 U CN 205541975U
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- heat exchanger
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- water
- core
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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
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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
Abstract
The utility model relates to a deep well formula ordinary pressure nuclear heating system, including reactor, a n ordinary pressure return circuit heat exchanger, distribution of energy current stabilizer, a m inertia voltage regulator device, a m intermediate loop heat exchanger of arranging the deep well in to and the well water forced cooling safety coefficient who reloads pond, spentnuclear fuel safety pool system and communicate with the deep well, n >= 2, m >= 2. The utility model discloses simple structure, agreeing with the heat supply and for the no haze of optimum matching, carbon -free discharge, high safe, economic new nuclear power source is equipped, having increased substantially the safety allowance of reactor, very effectual shielding radioactivity ensures safety, the cooling agent can not run off, effectively contains radioactive substance under the accident.
Description
Technical field
This utility model relates to well formula nuclear reactor heating field, particularly relates to cryogenic nucleus heating reaction in deep-well
Heap.
Background technology
All of power reactor (in addition to direct atomic boiler) all have employed so-called indirect cyclic process
Technology, if using this technology, reactor heat will be absorbed by first floor heat-conduction medium, then passes through
What indirect heat transfer was translated into available (being such as used for driving prime mover) gradually can gasifying liquid.
Therefore, this can only be indirectly connected with hot driving source by gasifying liquid.Those are thought and produces power
Steam be not dependent on its radiation can, and in most cases, even if in the event of fuel element fracture
Also, for people that can be unrelated with this type of radiation, their the urgent serious hope just of such system has.
Before this, indirect steam generator is typically all made up of the fissile material in reactor vessel,
Steam generator is placed in single heat exchange container, and this container is attached by pipeline, thus promotees
Entering the persistent loop of heat-conduction medium, the persistent loop of heat-conduction medium needs to start by pump machine and keep.
Later, the related needs processed for reactor maintenance maintenance and emergency, multiple heat-exchange devices are arranged
Within being listed in the loop placed that is parallel to each other.Therefore, a reactor is it is possible to there is multiple heat-exchange device
Service is provided for it.This type of circuit each is equipped with corresponding valve, is available for single heat-exchange device and ties up
Use when repairing maintenance or process emergency.
Deep-wall type normal pressure heat supplying nuclear reactor is a kind of low-temperature atmosphere-pressure heat reactor, and this reactor is operated in
At a temperature of relatively low, the heat energy that nuclear fission is produced by one, secondary circuit heat transfer system, pass to three loop pipe
Net each bypass region heat exchange station group, supply its terminal heat supply user group.At present, design both at home and abroad and construction
Low-temperature nuclear heat supplying pile be to utilize swimmer's pool, hydrostatic pressure improve the temperature of core exit water, thus reach
Improve the purpose of supply water temperature.
Up to the present research such as external Sweden, Russia etc. and construction pool type heating reactor, but have no subsequent forming
Development.At the end of domestic 1989, the shell-type low-temperature nuclear heat supplying pile that Tsing-Hua University's nuclear energy is built is successfully entered critical test run
OK.But overall structure is huge, corresponding anti-leak safety equipment imperfection.
Utility model content
For solving the problems referred to above, this utility model provides a kind of deep-wall type normal pressure core heating system, it is provided that
The hot water of corresponding load and temperature that heat supply needs, its simple in construction, agree with heat supply be optimal coupling without mist
Haze, non-carbon-emitting, the new nuclear power source equipment of high safety economy.The safety allowance of reactor is greatly improved,
Very effective shielding ensures radioactive substance safety；Coolant will not run off, and effectively contains and put under accident
Penetrating property material.Concrete scheme is as follows:
A kind of deep-wall type normal pressure core heating system, including deep-well reactor, n normal pressure loop heat exchanger, energy
Amount distribution constant-current stabilizer, m inertia stable-pressure device, m intermediate loop heat exchanger, and spentnuclear fuel safety
Cell system and the well water connected with deep-well force cooling security system, n >=2, m >=2；Wherein,
Described deep-well reactor includes: water-filled deep-well, be placed in the nuclear reactor core bottom deep-well, n
Decay cylinder, control rod group and numerically controlled intelligent drive mechanism thereof, residual heat of nuclear core with inertia water tank discharge system；
Described decay cylinder connects reactor core and normal pressure loop heat exchanger respectively；
Described reactor core is equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel；
Described residual heat of nuclear core discharges system waste heat in passive discharge deep-well, including being arranged on deep-well
The plate type heat exchanger in portion and be arranged on deep-well air above cooling tower, described plate type heat exchanger cools down with air
Plate air cooler in tower is connected；
Described decay cylinder is connected with the hot junction one_to_one corresponding of normal pressure loop heat exchanger, for being heated by described reactor core
Water be sent to described normal pressure loop heat exchanger；
Described energy distribution constant-current stabilizer is connected with the cold end of n normal pressure loop heat exchanger, respectively by described
Intermediate loop heat exchanger distributes the heat energy of different purposes and keeps the equal of energy distribution by inertia stable-pressure device
Weighing apparatus and the reduction disturbance to normal pressure loop；
Described m inertia stable-pressure device, for reducing the system impact on current, stablizes hydraulic pressure current, point
It is not arranged on the pipeline that energy distribution system is connected with intermediate loop heat exchanger；
Described m intermediate loop heat exchanger is connected with described energy distribution system respectively, for being passed by heat
Pass application；
Described spentnuclear fuel safe pool system includes water-filled spentnuclear fuel scratch pool, the spentnuclear fuel pond being sequentially communicated
And tank, described spentnuclear fuel scratch pool connects with deep-well；
Described well water forces cooling security system for the water cooling down, purifying in deep-well, cools down including band air
The chiller of equipment and purifier, described chiller and purifier respectively with the pipeline connecting deep-well
It is connected.
Further, described fresh fuel accounts for 10% the 60% of total amount, and described spentnuclear fuel accounts for the 40% of total amount
90%.
Further, it is stacked with spentnuclear fuel around described reactor core.
Further, the nuke rubbish that described spentnuclear fuel is used or external in being described reactor core.
Further, described control rod has many, and from below or top can be inserted in reactor core every control rod, institute
State its drive mechanism and control often to organize the up and down motion of control rod respectively, be used for carrying out power adjustments, shutdown and tight
Anxious situation processes.
Further, described normal pressure loop heat exchanger requires antidetonation simulation calculating, helium for meeting nuclear safety three grades
The heat exchanger of fine vacuum leak detection.
Further, photographic head is installed in described normal pressure loop heat exchanger both sides, and for scene, display monitors with teletransmission
Through longtime running.
Further, described m Intermediate Heat Exchanger is 2, and one of them is connected for concentrating with heating network
Heat supply, another is for sewage disposal, pure water production, desalinization or other purposes.
The beneficial effects of the utility model are:
Coolant of the present utility model will not run off, and effectively contains radioactive substance under accident.Cold at deep-well
But under agent water body pressure 0.2MPa (normal pressure): operating pressure is less than 0.2MPa, negating of heat supply low temperature
The running temperature answering heap is the lowest, and recirculated water is heated to 98 DEG C by 78 DEG C by nuclear fission release nuclear energy, by certainly
Dynamic regulation two-stage heat transmission system, according to the coldest, severe cold, end cold phase: the corresponding load providing heat supply to need with
The hot water of temperature, it is delivered into urban heating network and meets user's needs.
Under deep-well coolant water body pressure 0.2MPa (normal pressure): operating pressure is less than 0.2MPa, heat supply
The running temperature of the requirement reactor of low temperature is the lowest, and recirculated water is heated to by nuclear fission release nuclear energy by 78 DEG C
98 DEG C, the safety allowance of reactor being greatly improved, this utility model atmospheric low-temperature deep-wall type reactor does not has
There are the systems such as pressure vessel, containment and peace note, spray, are to utilize nuclear energy to meet heat supply needs most preferably to mate system
System.
The well water of deep-well and water body, ensure radioactive substance safety by very effective shielding, in maximum sky
Calamity man-made calamity includes that the armamentarium of passive discharge residual heat of nuclear core system all lost efficacy, and does not has human intervention
Under the conditions of, remaining to guarantee has 90 days nuclear safety intervention period.It is greatly simplified longevity after date full-shield on the spot and seals place up for safekeeping
Science and engineering journey.
Accompanying drawing explanation
Fig. 1 is structural representation of the present utility model；
Fig. 2 is that normal pressure loop heat exchanger structure of the present utility model arranges schematic top plan view.
Detailed description of the invention
Deep-wall type normal pressure core heating system of the present utility model is mainly used in heat production and transmission heat, is quiet with deep water
Pressure improves core exit water temperature, thus reaches to improve the purpose of supply water temperature, supplying high temperature difference heating network
In base heating load, circulating water temperature reaches 90/60 DEG C or 100/70 DEG C；Water outlet is through repeatedly radioactivity
Decay and radioactivity are isolated, and will not threaten environment and health of human body.Water heating is returned and supplies by reactor
Hot pipe network carries out group heat exchange to each subregion heat exchange station, and Zhongdao user's warmer releases effectively heat.
Between severe cold at full capacity short-term, heating system of the present utility model, reactor core nuclear fission heat energy by water by
78 DEG C are heated to 98 DEG C and reduce to through decay cylinder cooling, entrance normal pressure loop heat exchanger hot junction heat release
78 DEG C, return again to reactor core circulating-heating and cooled flow.Intermediate loop water is cold by normal pressure loop heat exchanger
Holding and by 74 DEG C, water is heated to 94 DEG C of inflow intermediate loop heat exchanger hot junctions, hot water heats in intermediate loop
Circulating with cooling, pressure heating network Loop Water passes through the cold side of intermediate loop heat exchanger by pipe network backwater
60 DEG C are heated to 90 DEG C, flow into heat absorption/heat release between the cold end of intermediate loop heat exchanger and pipe network and circulate.
Trembling with fear the phase with end in the coldest phase, reactor core nuclear reaction heat load increases along with atmospheric temperature declines heating demand
And increase, reach peak during to severe cold, enter the cold reactor core nuclear reaction heat load in end along with in atmospheric temperature
Rise heating demand to reduce.Control rod station is regulated, it is achieved the thermic load of nuclear reaction and change by drive mechanism
The heating demand of required change balance each other.Wherein normal pressure Loop Water flow is constant with return water temperature, core
Hot water temperature's change can be added；Intermediate loop discharge correspondence increase with reduce change, cold side water temperature 74 DEG C,
Hot side water temperature 94 DEG C not pressure changeable heating network Loop Water flow is constant with return water temperature with supplying hot water temperature.
Structure to a kind of well depth formula core heating system of the present utility model is done and is retouched further below in conjunction with the accompanying drawings
State:
As it is shown in figure 1, a kind of deep-wall type normal pressure core heating system of the present utility model, including in phreatic water
Deep-well reactor, 2 normal pressure loop heat exchangers, energy distribution constant-current stabilizer, 2 inertia stable-pressure devices, 2
Individual intermediate loop heat exchanger, and spentnuclear fuel safe pool system and the well water that connects with deep-well forces cooling safety
System.
Intermediate loop heat exchanger is 2, one of them be connected with pressure heating network loop flow into corresponding respectively
Individual heating plant be used for central heating, another for sewage disposal, pure water produce, desalinization or other
Purposes.
Deep-well reactor includes: water-filled deep-well, be placed in the nuclear reactor core bottom deep-well, decay cylinder,
Inertia water tank, control rod group and numerically controlled intelligent drive mechanism thereof, residual heat of nuclear core discharge system, and top is anti-flying
The removable well lid that row thing collides.Decay cylinder connects reactor core and normal pressure loop heat exchanger respectively, and decay cylinder connects
Inertia water tank.Control rod has many, and from below or top can be inserted in reactor core every control rod, drive mechanism
Control often to organize the up and down motion of control rod respectively, be used for carrying out power adjustments, shutdown and emergency and process.
The internal diameter 8-12m of deep-well, deep 10-150 rice, wall thickness 0.5-2.1m, base thickness 1-4m, serve as a contrast not inside the borehole wall
Rust steel wall is 0.3-0.8mm, and outside lining carbon steel wall is 5-15mm.Thick 1 2m of removable well lid.
Reactor core equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel, its ratio is: fresh fuel accounts for the 10% of total amount
60%, spentnuclear fuel accounts for 90% the 40% of total amount.The spentnuclear fuel just unloaded, weary combustion it is stacked with around reactor core
Material is nuke rubbish (such as: the Nuclear Power Station's Exhausted Fuels just unloaded) used or external in reactor core.
Residual heat of nuclear core discharges system waste heat in passive discharge deep-well, and it is positioned at the water on deep-well top
In, including being arranged on the plate type heat exchanger on deep-well top and being arranged on deep-well air above cooling tower (in figure
Not shown), welded plate type heat exchanger and the plate air cooler in air cooling compressor.Residual heat of nuclear core discharges system
Can lose power supply major accident time can passive discharge residual heat of nuclear core, ensure reactor core safety.
2 cylinder hot junctions respectively with 2 corresponding normal pressure loop heat exchangers of decaying are connected, for being added by reactor core
The water of heat is sent to normal pressure loop heat exchanger.Normal pressure loop heat exchanger requires antidetonation mould for meeting nuclear safety three grades
Intend the heat exchanger calculated, helium fine vacuum is hunted leak.Photographic head is installed in normal pressure loop heat exchanger both sides (in figure not
Illustrate), for scene, display monitors through longtime running with teletransmission.
High-order Large Copacity demineralized water water tank is connected with deep-well and normal pressure loop, and in good time moisturizing guarantees safety.
Spentnuclear fuel safe pool system includes water-filled fuel scratch pool, spentnuclear fuel pond and the water storage being sequentially communicated
Pond, fuel scratch pool connects with deep-well.Spentnuclear fuel pond, fuel scratch pool and deep-well reactor are connected to form greatly
Volumetric water system.
The heat transfer system of low temperature heap is a water circulating-heating, the process of heat-shift, low temperature heap heat transfer system
Water be the shape a low-temperature atmosphere-pressure state (water at reactor core is 3 atmospheric pressure, more than 100 degree Celsius)
The closed circuit carried out under state；Comparing the High Temperature High Pressure of nuclear power station, low temperature heap safety is higher.Meanwhile, low
Temperature heap can realize the waste heat cooling in loop by Natural Circulation, it is ensured that the non-energy of forced circulation to Natural Circulation
Dynamic conversion.
Normal pressure heat transfer loop include the valve in reactor core, decay cylinder, inertia water tank and normal pressure loop shielding machine room,
Normal pressure loop heat exchanger, water pump.Intermediate heat transfer loop includes the valve in intermediate loop machine room, intermediate loop
Heat exchanger, frequency conversion speed adjusting pump.
Energy distribution constant-current stabilizer for freely distributing, configure and the heat energy of Differential Output, and ensure whole in
Between the stablizing of loop fluid, reduce disturbance normal pressure loop fluid produced due to different heat distribution, configuration.
Energy distribution constant-current stabilizer is connected with the cold end of 2 normal pressure loop heat exchangers, respectively by intermediate loop heat exchange
The heat energy of the different purposes of device distribution also keeps the equilibrium of energy distribution by inertia stable-pressure device and reduces often
Push back the disturbance on the flow of road.
Inertia stable-pressure device, for reducing the system impact on current on pressure, stablizes hydraulic pressure current, respectively
It is arranged on the pipeline that energy distribution constant-current stabilizer is connected with intermediate loop heat exchanger.
2 intermediate loop heat exchangers are connected with described energy distribution system respectively, are used for transferring heat to city
City's pressure heating network.Normal pressure heat transfer loop, intermediate heat transfer loop, pressure heating network are one between loop
Individual progressively boost process；It is completely enclosed between each loop, and can not have any leakage, to prevent radiation
Pollutant enter urban heating network.
Well water forces cooling security system to be used for the water cooling down, purifying in deep-well, including band air cooling equipment
Chiller and purifier, described chiller and purifier respectively with the pipeline phase connecting deep-well
Even.Normal pressure loop, intermediate loop and well water force cooling security system to be provided entirely in underground, normal pressure loop
It is arranged at subsurface >=10m.When monitoring the radioactive wastewater water yield to limit value, start native system cooling
Purify, reach standard value stoppage in transit.Purifier includes: fore filter, cation and anion exchange mixed bed with
Resin catcher, its major function is as follows:
1, reactor water quality is controlled so that it is meet the water standard of regulation；
2, corrosion product and fission product content in water is reduced；
3, row's normal pressure heat transfer loop water is filled, it is ensured that water ordinary water level；
4, discharge water during maintenance；
5, top, pond pond water temperature is reduced.
Radioactive wastewater includes: normal pressure loop leakage water, radiology devices pipeline maintenance water, radiology devices
With Factory Building flushing water, equipment and pipeline chemical decontamination water, the sampling and analysing draining of normal pressure loop, radioactivity work
Make personnel's slurry and wash draining with working clothing.
This embodiment is merely to illustrate this utility model rather than limits scope of the present utility model, this area
Technical staff all falls within the application claims institute to the amendment of the various equivalent form of values of the present utility model
The scope limited.
Claims (8)
1. a deep-wall type normal pressure core heating system, it is characterised in that: include that deep-well reactor, n normal pressure return
Pipeline heat exchanger, energy distribution constant-current stabilizer, m inertia stable-pressure device, m intermediate loop heat exchanger, with
And spentnuclear fuel safe pool system and the well water pressure connected with deep-well cool down security system, n >=2, m >=2；Its
In,
Described deep-well reactor includes: water-filled deep-well, be placed in the nuclear reactor core bottom deep-well, n
Decay cylinder, control rod group and numerically controlled intelligent drive mechanism thereof, residual heat of nuclear core with inertia water tank discharge system；
Described decay cylinder connects reactor core and normal pressure loop heat exchanger respectively；
Described reactor core is equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel；
Described residual heat of nuclear core discharges system waste heat in passive discharge deep-well, including being arranged on deep-well
The plate type heat exchanger in portion and be arranged on deep-well air above cooling tower, described plate type heat exchanger cools down with air
Plate air cooler in tower is connected；
Described decay cylinder is connected with the hot junction one_to_one corresponding of normal pressure loop heat exchanger, for being heated by described reactor core
Water be sent to described normal pressure loop heat exchanger；
Described energy distribution constant-current stabilizer is connected with the cold end of n normal pressure loop heat exchanger, respectively by described
Intermediate loop heat exchanger distributes the heat energy of different purposes and keeps the equal of energy distribution by inertia stable-pressure device
Weighing apparatus and the reduction disturbance to normal pressure loop；
Described m inertia stable-pressure device, for reducing the system impact on current, stablizes hydraulic pressure current, point
It is not arranged on the pipeline that energy distribution system is connected with intermediate loop heat exchanger；
Described m intermediate loop heat exchanger is connected with described energy distribution system respectively, for being passed by heat
Pass application；
Described spentnuclear fuel safe pool system includes water-filled spentnuclear fuel scratch pool, the spentnuclear fuel pond being sequentially communicated
And tank, described spentnuclear fuel scratch pool connects with deep-well；
Described well water forces cooling security system for the water cooling down, purifying in deep-well, cools down including band air
The chiller of equipment and purifier, described chiller and purifier respectively with the pipeline connecting deep-well
It is connected.
2. core heating system as claimed in claim 1, it is characterised in that the mixed nucleus fuel in described reactor core
Ratio be: described fresh fuel accounts for 10% the 60% of total amount, and described spentnuclear fuel accounts for 40% the 90% of total amount.
3. core heating system as claimed in claim 1, it is characterised in that be stacked with weary combustion around described reactor core
Material.
4. the core heating system as described in claim 1,2 or 3, it is characterised in that described spentnuclear fuel is described
Nuke rubbish used or external in reactor core.
5. core heating system as claimed in claim 1, it is characterised in that described control rod has many, every
Control rod is from below or top can be inserted in reactor core, and its drive mechanism described controls often to organize the upper of control rod respectively
Lower motion, is used for carrying out power adjustments, shutdown and emergency and processes.
Core heating system the most according to claim 1, it is characterised in that described normal pressure loop heat exchanger is
Meet the heat exchanger that nuclear safety three grades requires that antidetonation simulation calculates, helium fine vacuum is hunted leak.
7. according to the core heating system described in claim 1 or 6, it is characterised in that described normal pressure loop heat exchange
Photographic head is installed in device both sides, and for scene, display monitors through longtime running with teletransmission.
Core heating system the most according to claim 1, it is characterised in that described m Intermediate Heat Exchanger is
2, one of them is connected for central heating with heating network, and another is for sewage disposal, pure
Water purification production, desalinization or other purposes.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520965887.8U CN205541975U (en) | 2015-11-27 | 2015-11-27 | Deep well formula ordinary pressure nuclear heating system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520965887.8U CN205541975U (en) | 2015-11-27 | 2015-11-27 | Deep well formula ordinary pressure nuclear heating system |
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| Publication Number | Publication Date |
|---|---|
| CN205541975U true CN205541975U (en) | 2016-08-31 |
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ID=56761587
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| CN201520965887.8U Active CN205541975U (en) | 2015-11-27 | 2015-11-27 | Deep well formula ordinary pressure nuclear heating system |
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| CN (1) | CN205541975U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105575449A (en) * | 2015-11-27 | 2016-05-11 | 田力 | Deep-well normal-pressure nuclear heating system |
-
2015
- 2015-11-27 CN CN201520965887.8U patent/CN205541975U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105575449A (en) * | 2015-11-27 | 2016-05-11 | 田力 | Deep-well normal-pressure nuclear heating system |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20171129 Address after: 100085 A, No. 9, Third Street, Shanghai Haidian District, Beijing, 9 layer A1003-105 Patentee after: Kai Xin Xin nuclear (Beijing) Energy Technology Co., Ltd. Address before: 100000 room B, room B, room 2, building 2, Beijing Zhongguancun software garden incubator, Northeastern Haidian District, Beijing Patentee before: X-NUCLEAR (BEIJING) ENERGY TECH. CO., LTD. |
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| TR01 | Transfer of patent right |