CN1514445A - Low temperature heat supply reactor having high safety - Google Patents
Low temperature heat supply reactor having high safety Download PDFInfo
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- CN1514445A CN1514445A CNA021590192A CN02159019A CN1514445A CN 1514445 A CN1514445 A CN 1514445A CN A021590192 A CNA021590192 A CN A021590192A CN 02159019 A CN02159019 A CN 02159019A CN 1514445 A CN1514445 A CN 1514445A
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- reactor
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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
- Y02A—TECHNOLOGIES FOR ADAPTATION TO CLIMATE CHANGE
- Y02A20/00—Water conservation; Efficient water supply; Efficient water use
- Y02A20/124—Water desalination
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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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Abstract
A pressure accumulation water-tank located at one side of container of the reactor core is 10-30m higher than top of the reactor core. A filling pipe at bottom of the water-tank is connected to an inlet pipe of core refrigerant. Rising pipe from outlet pipe of core refrigerant passing through the water-tank is 5-30 cm higher than water surface in water-tank. Hydrostatic pressure type mechanism for driving control rods utilizes two sets of independent shutdown systems. Leading out of surplus heat and safe watering are carried out by water-tank. Raising plate type hot vaporizer having intermediate course reduces loops in interspace as well as size of equipment and manufacturing cost. The shutdown systems make the reactor core possess high intrinsic safety. The reactor core will never be melted or burned and meet requirement of 'zero radioactivity' for environment under condition of any accidents. The reactor core is applied to heat supply in low temperature and seawater desalination.
Description
Technical field
The present invention relates to a kind of nuclear reactor technology, specifically a kind of low temperature heating reactor of height inherent safety.
Background technology
Utilizing nuclear heating is an important means that solves heating and desalinization.Although low-temperature heat supply nuclear reactor conceptual design kind is a lot of both at home and abroad at present, but because economy and security are not also accepted extensively by people, especially low-temperature heat supply adjust the distance densely populated zone can not be too far away, nuclear safety is even more important, therefore will seek the higher and cheap heap type of inherent safety, this is the key that decision nuclear heating heap is promoted.
Summary of the invention
The object of the present invention is to provide higher, the cheap inherently safe low temperature heating reactor of a kind of height of a kind of inherent safety, carry out low-temperature heat supply and desalinization.
The technical scheme that realizes the object of the invention is: the side at reactor vessel is provided with a pressure accumulation pond that exceeds reactor core top 10～30m, the pressure accumulation basin bottom is provided with an ascending pipe, this ascending pipe communicates with the reactor coolant induction pipe, ascending pipe is provided with the inverted U tube portion, purpose is to pass to the pressure accumulation pond for heat in preventing to pile, and also has one to be drawn by the reactor coolant outlet and to pass the tedge that the pressure accumulation pond exceeds the pond water surface 5～30cm.The vertical shaft sealing that is made of concrete around these two pipes prevents that pipeline damage from causing the pond leakage.Control rod drive mechanisms (CRD) is arranged on the ball-type top cover of core vessel.The reactor coolant outlet is connected through the plate fin heat-exchanging evaporator inlet of isolation valve with the band intermediate course, and the outlet of plate fin heat-exchanging evaporator is connected with another isolation valve with main pump respectively, and this isolation valve is connected with the reactor coolant induction pipe.
Utilize the hydraulic type control rod drive mechanisms (CRD) of hydraulic piston principle, its base is connected with the core vessel top cover, and a side of base cavity is provided with pipeline, communicates with pump discharge pipe.In the center pit of piston and the center pit of guide housing driving stem is installed, is provided with spring between briquetting and piston, this spring inboard is provided with the gripper of driving stem, and this gripper cooperates with the driving stem groove and blocks.The upper end of pneumatic shell is provided with pumping intake piping, pumping into of the upper and lower cavity of pneumatic shell is provided with the short circuit pipe between the outlet, on the short circuit pipe solenoid valve is installed, reaches the outage of " reactor core temperature in height " signal controlling solenoid valve by " heap power is too high ", " core exit temperature height ", solenoid valve is opened automatically.When piston during in the bottom, the briquetting holddown spring makes gripper catch driving stem, and the pump startup back piston is stressed to be moved upward to till the top.Pressure reduction is reduced to a certain degree (pump outage or solenoid valve are opened) about piston, piston falls, this moment, briquetting was held to fall by pneumatic shell top electromagnet, by spring force gripper is opened like this, driving stem hurtles down, and piston falls at a slow speed, when the electromagnet outage, briquetting falls, and is ready to next time according to rod.
Effect of the present invention: owing to be provided with from the pressure accumulation pond that goes out the reactor core top, improved core exit pressure, the fluctuation of core vessel water capacity, waste heat are derived and safety injection four big functions.Especially any valve that need not to move can be realized waste heat derivation and safety injection.Utilize the plate fin heat-exchanging evaporator of band intermediate course to replace heat interchanger and revaporizer, reduced intermediate loop, reduced equipment size, reduce cost.Utilize the hydraulic type control rod drive mechanisms (CRD) of hydraulic piston principle, form two and overlap independently reactor shut-off system, make this heap have the height inherent safety like this, reactor core never melts, never burns in anything event operating mode and all satisfy environment " "dead" consequence " requirement.This low temperature heating reactor, inherent safety is higher, cheap, can be used for carrying out low-temperature heat supply and desalinization.
Accompanying drawing and explanation
Fig. 1 is the inherently safe low temperature heating reactor synoptic diagram of height of the present invention.
Fig. 2 is a hydraulic type control rod drive mechanisms (CRD) synoptic diagram of the present invention.
Among the figure:
1. reactor core, 2. core vessel, 3. reactor core hangs indigo plant, 4. heap container cap, 5. control rod drive mechanisms (CRD), 6. reactor coolant outlet, 7. reactor coolant inlet tube, 8. isolation valve, 9. heat exchange evaporator, 10. main pump, 11. vertical shafts, 12. tedges, 13. ascending pipe, 14. pressure accumulation ponds, 15. upper limit position detectors, 16. electromagnet, 17. pneumatic shells, 18. lower position detectors, 19. driving stem, 20. briquettings, 21. grippers, 22. spring, 23. pistons, 24. bases, 25. guide housing, 26. pump discharge, 27. solenoid valves, 28. pump intakes.
Embodiment
The present invention is an example with the process heat reactor of a thermal power 200MW, and its structure as shown in Figure 1.
This heap should be called Chi Keshidui, and the pool type reactor characteristics are promptly arranged, and the sealing core vessel is arranged again.Reactor core 1 is placed on core vessel 2 lower central, fixed by hanging blue 3, hanging blue 3 hangs between the reactor coolant outlet 6 and reactor coolant inlet tube 7 of core vessel 2, the cooling medium intake-outlet is isolated, remove coolant outlet 6 pipe and the complicated hermetically-sealed construction that hangs between blue 3 from, core vessel 2 leans on upper support on the reactor core concrete shielding.Control rod drive mechanisms (CRD) 5 is arranged on the ball-type heap container cap 4 of core vessel 2, is rigidly connected with the control rod absorber.
Major cycle water flows out from reactor coolant outlet 6 during normal the operation, enters the plate fin heat-exchanging evaporator 9 of being with intermediate course through isolation valve 8, and the water after the cooling is piled for 7 times through another isolation valve 8, reactor coolant inlet tube through main pump 10 superchargings again.
Utilize the plate fin heat-exchanging evaporator substituting disposable heat interchanger and the revaporizer of band intermediate course, reduce intermediate loop, reduce equipment size, reduce cost.
But plate fin heat-exchanging evaporator intermediate course water-filling, inflated with nitrogen also can be taken out the certain vacuum degree, and whether supervise the heat interchanger dividing plate with the variation of interlayer pressure has leakage.
Side at core vessel 2 is provided with a pressure accumulation pond 14 that exceeds reactor core 1 top 10-30m, 14 bottoms, pressure accumulation pond are provided with an ascending pipe 13 and communicate with reactor coolant inlet tube 7, ascending pipe 13 is provided with the inverted U tube portion, and purpose is to pass to pressure accumulation pond 14 in order to intercept the interior heat of heap; Drawing one by reactor coolant outlet 6 passes pressure accumulation pond 14 and exceeds pond water surface 5-30cm tedge 12.Tedge 12 and vertical shaft 11 sealings that are made of concrete around the ascending pipe 13 prevent that pipeline damage from causing the pond leakage.
When trunk line ruptured, to reactor core 1 water filling, volume was as far as possible little between major loop by ascending pipe 13, takes the seal isolation measure, guaranteed that the water that bleeds between major loop no longer outwards spills.
After main pump 10 starts, water level is lower than pressure accumulation pond 14 water levels in the tedge 12, the height that reduces equates with reactor core 1 pressure drop, behind the reactor hoisting power, water temperature raises near the water temperature of reactor coolant outlet 6 in the tedge 12, tedge 12 water levels rise, but still are lower than tedge 12 outlets, and Natural Circulation can not form.After the external power outage, descend by reactor core 1 flow, when reactor core 1 pressure drop was decreased to a certain degree, tedge 12 emitted water, formed Natural Circulation.Therefore, when hoisting power or power swing, keep reactor core pressure by water injection pipe.Power cut-off or normal shutdown outside stops some main pumps and need not to move any valve and realize that passive residual heat derives.The reactor core heat is passed to the pressure accumulation pond, and when the pressure accumulation pond water yield was enough big, ultimate heat sink can be done in the pressure accumulation pond, realizes emergent waste heat derivation.
Under pipeline large break accident, reactor core pressure descends rapidly, and this moment, cistern to a large amount of water fillings of reactor core, made reactor core be in floodage forever by potential difference, after water is full of between major loop, still utilized cistern to keep reactor core pressure.
There are four big functions in high water stage pressure accumulation pond: pressurization, water capacity fluctuation, non-passive safety injection, passive residual heat are derived, herein cistern also when reloading to the reactor pit water-filling and the storage of unloading water outlet.
Because low temperature heating reactor power is bigger, ATWS, removal of load ATWS and rod withdrawal ATWS will consider to cut off the power supply when design.Best bet is that the second cover reactor shut-off system is set, and that is to say on the basis of magnetic resistance motor control rod drive mechanisms (CRD), has increased the hydraulic type control rod drive mechanisms (CRD).
Utilize the hydraulic type control rod drive mechanisms (CRD) of hydraulic piston principle, as shown in Figure 2.Base 24 is connected with heap container cap 4, and a side of base 24 cavitys is provided with the pipeline that is connected with pump discharge 26.Guide housing 25 is installed in the lower end of base 24, the upper end of base 24 is equipped with pneumatic shell 17, be provided with piston 23 in the pneumatic shell 17, driving stem 19 is installed in the center pit of the center pit of piston 23 and guide housing 25, in pneumatic shell 17, the outside of driving stem 19 is provided with briquetting 20, be provided with spring 22 between briquetting 20 and piston 23, spring 22 inboards are provided with the gripper 21 of driving stem 19, and this gripper 21 cooperates with the groove of driving stem and blocks.The upper end of pneumatic shell 17 is provided with the pipeline 28 that is connected with pump intake, is provided with the short circuit pipe between the pipeline of the pipeline of pump discharge 26 and pump intake 28, and solenoid valve 27 is installed on the short circuit pipe.Be provided with electromagnet 16 and upper limit position detector 15 on the top cover of pneumatic shell 17 successively, the lateral wall of pneumatic shell 17 is provided with lower position detector 18.
Gripper 21 is caught driving stem 19 under briquetting 20 gravity when control rod inserts the bottom, by 18 indications of lower position detector, after main pump 10 starts, utilize main pump 10 or coaxial little water pump inlet outlet pressure differential to push piston 23 to top, the control rod that links to each other promptly proposes reactor core, and remain on upper position, by 15 indications of upper limit position detector, when solenoid valve 27 outage open or the water pump inlet outlet pressure differential little of to a certain degree, piston 23 falls, briquetting 20 is still stayed top by electromagnet 16 suction, gripper 21 is opened driving stem 19 and is hurtled down the end of to like this, piston 23 slowly falls, when needs electromagnet outage several seconds during rod withdrawal once more, briquetting 20 whereabouts holddown springs 22 also move gripper 21 to catch driving stem 19 to get final product rod withdrawal inwards.
Utilize the hydraulic piston principle, after main pump starts, can utilize main pump inlet outlet pressure differential (the coaxial water pump inlet outlet pressure differential of also available main pump) that piston is pushed to portion, continuous control rod promptly proposes reactor core, and back piston drives the control rod whereabouts when the main pump flow is reduced to a certain degree.Reach hot shutdown even can cross cold shut, so just do not have outage ATWS.The short circuit pipe that connects a charged magnet valve in addition at the upper and lower cavity of the pneumatic shell 17 of piston 23, the solenoid valve of short circuit pipe is opened piston 23 upper and lower cavity pressure reduction and is disappeared, piston 23 falls, and the valve on this short circuit pipe to be normally open solenoid valve energising close, power-off signal is heap power core exit temperature and reactor core temperature in.So just can avoid removal of load ATWS, rod withdrawal ATWS accident.
Claims (7)
1. highly inherently safe low temperature heating reactor, its reactor core is by in the core vessel that hangs indigo plant and be located at sealing, core vessel is provided with reactor coolant outlet and reactor coolant induction pipe, the core vessel upper support is on the reactor core concrete shielding, control rod drive mechanisms (CRD) is arranged on the top cover of core vessel, reactor coolant outlet on the core vessel is connected with the outer heat exchange evaporator of reactor coolant induction pipe and reactor core concrete shielding, it is characterized in that being provided with a pressure accumulation pond that exceeds reactor core top 10～30m in a side of core vessel, the pressure accumulation basin bottom is provided with an ascending pipe and communicates with the reactor coolant induction pipe, draws one by the reactor coolant outlet and passes the pressure accumulation pond and exceed the pond water surface 5～30cm tedge.
2. the inherently safe low temperature heating reactor of height as claimed in claim 1 is characterized in that plate fin heat-exchanging evaporator substituting disposable heat interchanger and revaporizer with the band intermediate course, reduces intermediate loop.
3. the inherently safe low temperature heating reactor of height as claimed in claim 1, it is characterized in that: described control rod drive mechanisms (CRD) has two covers, and a cover is magnetic foot motor type, and a cover is hydraulic type.
4. the inherently safe low temperature heating reactor of height as claimed in claim 1 is characterized in that the vertical shaft that is made of concrete around tedge and the ascending pipe seals.
5. the inherently safe low temperature heating reactor of height as claimed in claim 1 is characterized in that ascending pipe is provided with the inverted U tube portion.
6. as claim 1 or the inherently safe low temperature heating reactor of 3 described height, it is characterized in that described hydraulic type control rod drive mechanisms (CRD), one side of the cavity of its base is provided with pump discharge pipe, the upper end of base is equipped with pneumatic shell, be provided with piston in the pneumatic shell, the center pit of piston is installed driving stem, in the pneumatic shell, the outside of driving stem is provided with briquetting, between briquetting and piston, be provided with spring, the spring inboard is provided with the gripper of driving stem, this gripper cooperates with groove on the driving stem and blocks, the pneumatic shell upper end is provided with pumping intake piping, be provided with the short circuit pipe of charged magnet valve between pumping intake piping and the pump discharge pipe, be provided with electromagnet and upper limit position detector on the top cover of pneumatic shell successively, the lateral wall of pneumatic shell is provided with the lower position detector.
7. the inherently safe low temperature heating reactor of height as claimed in claim 6 is characterized in that being provided with guide housing in the lower end of base the center pit centering of the center pit of this guide housing and piston.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB021590192A CN1208781C (en) | 2002-12-27 | 2002-12-27 | Low temperature heat supply reactor having high safety |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB021590192A CN1208781C (en) | 2002-12-27 | 2002-12-27 | Low temperature heat supply reactor having high safety |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1514445A true CN1514445A (en) | 2004-07-21 |
| CN1208781C CN1208781C (en) | 2005-06-29 |
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| Application Number | Title | Priority Date | Filing Date |
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| CNB021590192A Expired - Lifetime CN1208781C (en) | 2002-12-27 | 2002-12-27 | Low temperature heat supply reactor having high safety |
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| CN (1) | CN1208781C (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN100578682C (en) * | 2005-09-29 | 2010-01-06 | 中国核动力研究设计院 | Passive special safety facility for reactor |
| CN101079333B (en) * | 2006-05-26 | 2010-07-14 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
| CN104091621A (en) * | 2014-07-24 | 2014-10-08 | 哈尔滨工程大学 | Passive out-of-reactor cooling system |
| CN107910079A (en) * | 2017-10-31 | 2018-04-13 | 田嘉夫 | Swimmer's pool heat supplying nuclear reactor pond inner structure and fuel handling method |
| CN111370148A (en) * | 2018-12-25 | 2020-07-03 | 国家电投集团科学技术研究院有限公司 | Two sets of shutdown mechanisms of reactor and reactor |
| WO2020142500A1 (en) * | 2018-12-31 | 2020-07-09 | Ge-Hitachi Nuclear Energy Americas Llc | Underground vertical shafts and nuclear reactors using the same |
| CN112066043A (en) * | 2020-07-31 | 2020-12-11 | 清华大学 | Control rod drive line combination valve structure and control rod hydraulic drive system |
-
2002
- 2002-12-27 CN CNB021590192A patent/CN1208781C/en not_active Expired - Lifetime
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN100578682C (en) * | 2005-09-29 | 2010-01-06 | 中国核动力研究设计院 | Passive special safety facility for reactor |
| CN101079333B (en) * | 2006-05-26 | 2010-07-14 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
| CN104091621A (en) * | 2014-07-24 | 2014-10-08 | 哈尔滨工程大学 | Passive out-of-reactor cooling system |
| CN104091621B (en) * | 2014-07-24 | 2016-08-03 | 哈尔滨工程大学 | Passive out-pile cooling system |
| CN107910079A (en) * | 2017-10-31 | 2018-04-13 | 田嘉夫 | Swimmer's pool heat supplying nuclear reactor pond inner structure and fuel handling method |
| CN111370148A (en) * | 2018-12-25 | 2020-07-03 | 国家电投集团科学技术研究院有限公司 | Two sets of shutdown mechanisms of reactor and reactor |
| CN111370148B (en) * | 2018-12-25 | 2024-05-14 | 国家电投集团科学技术研究院有限公司 | Two sets of shutdown mechanisms of reactor and reactor |
| WO2020142500A1 (en) * | 2018-12-31 | 2020-07-09 | Ge-Hitachi Nuclear Energy Americas Llc | Underground vertical shafts and nuclear reactors using the same |
| CN112066043A (en) * | 2020-07-31 | 2020-12-11 | 清华大学 | Control rod drive line combination valve structure and control rod hydraulic drive system |
| CN112066043B (en) * | 2020-07-31 | 2021-09-03 | 清华大学 | Control rod drive line combination valve structure and control rod hydraulic drive system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN1208781C (en) | 2005-06-29 |
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Granted publication date: 20050629 |