CN201638576U - Emergent reactor core cooling system of pool-type reactor - Google Patents
Emergent reactor core cooling system of pool-type reactor Download PDFInfo
- Publication number
- CN201638576U CN201638576U CN2010201260145U CN201020126014U CN201638576U CN 201638576 U CN201638576 U CN 201638576U CN 2010201260145 U CN2010201260145 U CN 2010201260145U CN 201020126014 U CN201020126014 U CN 201020126014U CN 201638576 U CN201638576 U CN 201638576U
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- Prior art keywords
- reactor
- heat exchanger
- emergency pump
- type heat
- pump
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Links
- 238000001816 cooling Methods 0.000 title claims abstract description 25
- 238000005859 coupling reaction Methods 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 10
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 6
- 239000002918 waste heat Substances 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 230000009182 swimming Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
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Classifications
-
- 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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model discloses an emergent reactor core cooling system of a pool-type reactor, comprising an emergent pump, a passive valve and a plate-type heat exchanger (5). The inlet end of the emergent pump is communicated with a reactor pool, the output end of the emergent pump is connected with the passive valve which is connected with a reactor cooling main loop system (4), the output end of the emergent pump is also connected with the plate-type heat exchanger (5) which is communicated with the reactor pool, and the passive valve is arranged between the plate-type heat exchanger (5) and the emergent pump. The utility model has simple structure, saves energy, lessens the interference of operators, reduces the start failures of equipment and automatically operates.
Description
Technical field
The utility model relates to reactor core cooling field, particularly a kind of pool reactor emergence core stacking cool system.
Background technology
For the nuclear power station presurized water reactor, generally be provided with special-purpose residual heat removal system and emergent a whole set of engineered safeguards features that cools off of reactor core under the accident conditions is provided, and be provided with auxiliary feedwater system, device cooling system and the critical services water system etc. that waste heat transferred to ultimate heat sink.And the shutdown of research reactor cooling normally realizes that than simple mechanism and facility the waste heat of reactor core discharges relatively by some.
101 heavy water research reactors of atomic energy institute, nominal situation and accident conditions all are to discharge residual heat of nuclear core by the heavy water pump, and what just use under accident conditions is reliable power supply power supply.49-2 swimming pool formula light-water reactor, nominal situation remain in operation by main pump down and take residual heat of nuclear core out of, and accident conditions starts by battery-driven accident pump by the low excessively guard signal of major loop flow down, carries out the waste heat discharge function.Since the power ratio of 101 heavy water reactor and 49-2 swimming pool formula light water reactor lower (be respectively 10MW, 2MW), so its main pump all is not provided with inertial flywheel.
At present, all there is following problem in domestic and international research heap execution emergence core stacking cool system:
(1) system does not generally start at ordinary times, and accident conditions start, and equipment is idle at ordinary times, exists to start the problem that lost efficacy.
Insert when (2) system's generalized case is for accident or switch and fall reliable source of power, be power supply commonly used at ordinary times.Need the operator to move, also there is the startup Problem of Failure in diesel engine.
(3) system's access way is unreliable, needs operating personnel to intervene.Can not guarantee, easily make mistakes turn-on time.
(4) partial reaction heap accident conditions also need the hot trap of secondary of emergency service.System complex, power supply is complicated.
Summary of the invention
The utility model has overcome deficiency of the prior art, provides a kind of simple in structure, saves the energy, reduces operating personnel and intervenes, and reduces the device start fault, the pool reactor emergence core stacking cool system that puts into operation automatically.
In order to solve the problems of the technologies described above, the utility model is achieved through the following technical solutions:
A kind of pool reactor emergence core stacking cool system, comprise emergency pump, non-energy movable valve, plate type heat exchanger, the emergency pump inlet end is communicated with reactor pit, the endpiece of emergency pump can be connected by movable valve with non-, non-energy movable valve coupled reaction cooling in heap is system but, and key is that the endpiece of emergency pump also connects plate type heat exchanger, plate type heat exchanger is communicated with reactor pit, is provided with non-energy movable valve between plate type heat exchanger and the emergency pump.
The utility model is all right: described emergency pump is that two emergency pumps compose in parallel.
Compared with prior art, the beneficial effects of the utility model are: this system moves simultaneously by adopting emergency pump and reactor, and the mode by UPS power supply, so fundamentally solve emergency pump under the accident conditions and started and lost efficacy and the problem of operating personnel maloperation, improved the reliability of emergence core stacking cool system; Simultaneity factor adopts non-energy movable valve, and emergency function automatically performs, and needing under the accident conditions to have avoided operating personnel to intervene and equipment action Problem of Failure.After gathering, emergency system outlet bypass can realize pond water cooling function through 1 pond water-to-water heat exchanger.
Description of drawings
The structural representation of Fig. 1 system
Embodiment
Below in conjunction with accompanying drawing and embodiment the utility model is described in further detail:
A kind of pool reactor emergence core stacking cool system, comprise emergency pump, non-energy movable valve, plate type heat exchanger 5, the emergency pump inlet end is communicated with reactor pit, the endpiece of emergency pump can be connected by movable valve with non-, non-energy movable valve coupled reaction cooling in heap is primary heat transport system 4 but, the endpiece of emergency pump also connects plate type heat exchanger 5, and plate type heat exchanger 5 is communicated with reactor pit, is provided with non-energy movable valve between plate type heat exchanger 5 and the emergency pump.Two emergent cooling ducts that described emergency pump adopts two emergency pump 1a, 1b parallel-connection structure to form.Wherein two emergency pump 1a, 1b in the present embodiment adopt the uninterrupted power supply (ups) Unity power supply; Non-energy movable valve 3a is installed between emergency pump 1a and the plate type heat exchanger 5, non-energy movable valve 3b is installed between emergency pump 1b and the plate type heat exchanger 5; Non-energy movable valve 2a is set between emergency pump 1a and the reactor cooling primary heat transport system 4, non-energy movable valve 2b is set between emergency pump 1b and the reactor cooling primary heat transport system 4.UPS keeps emergency pump 1a, 1b and moves 2 hours continuously under forfeiture off-site power situation, at this moment between in the forced circulation that provides of emergency pump 1a, 1b be enough to discharge residual heat of nuclear core;
Be designed to normally open for the system's bypass valve that requires that satisfies automatic executing function simultaneously, two emergency pump 1a, 1b absorb water from reactor pit during nominal situation, because cooling primary heat transport system 4 pressure height, non-energy movable valve 2a, 2b on system's main pipe rail be in closed condition, the emergency system bypass is passed through non-energy movable valve 3a, 3b to plate type heat exchanger 5, and the Chi Shui of cooling is refilled in the reactor pit.
When accident conditions, reactor cooling primary heat transport system 4 pressure reduce, non-can movable valve 2a, 2b opening automatically on the cooling primary heat transport system 4, cooling primary heat transport system 4 is worked simultaneously with emergency system, and the flow in the pipeline mates automatically realizes the emergency system functional requirement.The switching of this design between each operating mode is non-fully active, and emergency function automatically performs, and this needs operating personnel to intervene the problem that action was lost efficacy with equipment with regard to having been avoided under the accident conditions.
The concrete operational process of native system is as follows:
Native system adopts jumbo stillpot water as emergent hot trap.
When normal reactor operation, emergency pump 1a, 1b are with stack operation, because reactor cooling primary heat transport system 4 pressure are far above emergency pump 1a, 1b top hole pressure, its non-energy movable valve 2a, 2b be in closed condition all the time, emergency pump 1a, 1b can not inject reactor cooling primary heat transport system 4, but make Chi Shui obtain cooling through plate type heat exchanger 5 through by-pass, carry out pond water cooling function.It is 125m that present embodiment adopts the flow of separate unit emergency pump
3/ h, bypass house steward are 250m
3/ h.
When " losing hot trap " incident takes place in reactor, by the emergency shut-down of " coolant outlet temperature is too high " signal triggering reactor, main circulation pump is out of service automatically, reactor cooling this moment primary heat transport system 4 pressure reduce, non-can movable valve 2a, 2b opening automatically, emergency pump 1a, 1b are delivered to reactor cooling primary heat transport system 4 with stillpot water, and then guarantee to have 180m at least in the reactor
3Flow through under last reactor core and take the reactor core liberated heat out of of/h cooling flow.
Claims (3)
1. pool reactor emergence core stacking cool system, comprise emergency pump, non-energy movable valve, plate type heat exchanger (5), the emergency pump inlet end is communicated with reactor pit, the endpiece of emergency pump can be connected by movable valve with non-, non-energy movable valve coupled reaction cooling in heap is primary heat transport system (4) but, it is characterized in that the endpiece of emergency pump also connects plate type heat exchanger (5), plate type heat exchanger (5) is communicated with reactor pit, is provided with non-energy movable valve between plate type heat exchanger (5) and the emergency pump.
2. a kind of pool reactor emergence core stacking cool system according to claim 1 is characterized in that, described emergency pump is that two emergency pumps (1a, 1b) compose in parallel.
3. a kind of pool reactor emergence core stacking cool system according to claim 1 is characterized in that, described emergency pump adopts the uninterrupted power supply (ups) Unity power supply.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010201260145U CN201638576U (en) | 2010-03-09 | 2010-03-09 | Emergent reactor core cooling system of pool-type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010201260145U CN201638576U (en) | 2010-03-09 | 2010-03-09 | Emergent reactor core cooling system of pool-type reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201638576U true CN201638576U (en) | 2010-11-17 |
Family
ID=43083081
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2010201260145U Expired - Lifetime CN201638576U (en) | 2010-03-09 | 2010-03-09 | Emergent reactor core cooling system of pool-type reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201638576U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103174872A (en) * | 2013-03-20 | 2013-06-26 | 华北电力大学 | Passive valve system driven by temperature difference |
| CN104303236A (en) * | 2012-04-11 | 2015-01-21 | 原子能技术公司 | Nuclear reactor having plate or micro-channel heat exchangers integrated in the vessel |
| CN109659046A (en) * | 2019-02-01 | 2019-04-19 | 中国原子能科学研究院 | The reactor waste guiding system of coupling |
| CN111883270A (en) * | 2020-08-26 | 2020-11-03 | 中国原子能科学研究院 | Heat removal system, pool reactor, and pool reactor heat removal method |
-
2010
- 2010-03-09 CN CN2010201260145U patent/CN201638576U/en not_active Expired - Lifetime
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104303236A (en) * | 2012-04-11 | 2015-01-21 | 原子能技术公司 | Nuclear reactor having plate or micro-channel heat exchangers integrated in the vessel |
| CN104303236B (en) * | 2012-04-11 | 2016-12-21 | 原子能技术公司 | There is the nuclear reactor of integrated board-like or micro channel heat exchanger in a reservoir |
| CN103174872A (en) * | 2013-03-20 | 2013-06-26 | 华北电力大学 | Passive valve system driven by temperature difference |
| CN109659046A (en) * | 2019-02-01 | 2019-04-19 | 中国原子能科学研究院 | The reactor waste guiding system of coupling |
| CN111883270A (en) * | 2020-08-26 | 2020-11-03 | 中国原子能科学研究院 | Heat removal system, pool reactor, and pool reactor heat removal method |
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| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20101117 |
|
| CX01 | Expiry of patent term |