CN105719706A - Small reactor passive core cooling system - Google Patents
Small reactor passive core cooling system Download PDFInfo
- Publication number
- CN105719706A CN105719706A CN201410719385.7A CN201410719385A CN105719706A CN 105719706 A CN105719706 A CN 105719706A CN 201410719385 A CN201410719385 A CN 201410719385A CN 105719706 A CN105719706 A CN 105719706A
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- 238000001816 cooling Methods 0.000 title claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 113
- 239000002826 coolant Substances 0.000 claims abstract description 35
- 238000010992 reflux Methods 0.000 claims description 8
- 229910000831 Steel Inorganic materials 0.000 claims description 7
- 239000007788 liquid Substances 0.000 claims description 7
- 239000010959 steel Substances 0.000 claims description 7
- 238000000926 separation method Methods 0.000 claims description 4
- 238000010276 construction Methods 0.000 claims description 3
- 239000012530 fluid Substances 0.000 claims description 2
- 238000002347 injection Methods 0.000 abstract description 4
- 239000007924 injection Substances 0.000 abstract description 4
- 230000001629 suppression Effects 0.000 abstract 1
- 238000005516 engineering process Methods 0.000 description 4
- 230000005484 gravity Effects 0.000 description 4
- 230000035515 penetration Effects 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
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 present invention discloses a small reactor passive core cooling system including a water replenishing tank, pipes of the water replenishing tank, a safe water injection pool, pipes of the safe water injection pool, a residual heat exchanger, pipes of the residual heat exchanger and a circle-structure shielding water pool, the circle-structure shielding water pool is arranged around a pressure vessel, the circle-structure shielding water pool is provided with a suppression pipe ad a water pipe, a pressure relief pipe is arranged between the shielding water pool and a reactor coolant, and the pressure relief pipe is used for communication of the reactor coolant and a water body in the shielding water pool, and is provided with a valve group. The small reactor passive core cooling system can be used as an important part of a passive safety system of a small containment vessel to achieve the functions of taking away reactor core decay heat and providing a safe water injection source in accidents, and can effectively suppress containment vessel peak pressure. The system equipment layout is compact, space occupation is small, arrangement is simple, and economical efficiency is high.
Description
Technical field
The present invention relates to the security system design field of nuclear power plant reactor, relate in particular to the passive core cooling system of a kind of Small reactor.
Background technology
The core cooling system of nuclear power station belongs to a part for security system, and its major function is to take reactor core decay heat after accident out of and keep core deluge.The commonly used active technology of second filial generation pressurized-water reactor nuclear power plant (such as Daya Bay nuclear power plant etc.), namely utilizes external power source, relies on pump head to drive cooling circuit operating, it is achieved to remove reactor core decay heat and the function to reactor core water filling.Three generations's pressurized-water reactor nuclear power plant (such as three nuclear power stations) commonly used passive technology, namely relies on the natural driving forces such as gravity, Natural Circulation, compression air expansion, drives loop operating, it is achieved security function.Along with the development of technology and the raising to nuclear plant safety requirement, passive safety system will become designer trends.
Small modular reactor (SMR) refers generally to the power modularity presurized water reactor lower than 300MWe, and its principal character includes: miniaturization, integration, modularity and non-passive safety.From modularity and economy point, SMR is preferably configured the containment that volume is relatively small.But for passive safety system, small-sized safety shell faces problems with:
1, when loss of-coolant accident (LOCA) (LOCA) that generator tube road cut causes, small-sized safety shell is less due to volume, causes that boosting is too fast too high, there is superpressure and the risk of penetration piece seal failure；
When 2, there is LOCA accident, reactor is in pressure reduction, it is necessary to inject cooling water source, it is ensured that core deluge.Although high pressure phase can arrange Core makeup tank, but periods of low pressure needs to provide the peace water filling source of more big yield, but spaces compact in small-sized safety shell, it is difficult to arrange special low pressure peace water-filled pool；
3, after accident, reactor core decay heat discharges reactor core typically via heat-rejection circuit.Although residual heat removal loop can be arranged, but this loop needs the intermediate heat trap that rejects heat in containment.But spaces compact in small-sized safety shell, it is difficult to arrange the special pond for absorbing heat-rejection circuit heat.
4, passive system generally arranges depressurized circuit, to actively control reactor stress-relief process when accident.Owing to containment volume is little, the terminal of depressurized circuit is preferably disposed in hydrospace, it is to avoid unloads the steam pressed out and brings pressure to bear to containment, but is difficult to equally in small-sized safety shell arrange the pond for absorbing depressurized circuit heat.
5. the major accident for usually considering in presurized water reactor safe design, is generally adopted the means that in heap, fused mass is detained, but this means needs to have in containment the water source of abundance.Equally, small-sized safety shell due to volume little, it is impossible to arrange special water source.
Summary of the invention
For the problems referred to above, the present invention provides the passive core cooling system of a kind of Small reactor, Safety System Design suitable in small-sized safety shell, realize under accident, taking away reactor core decay heat, peace water filling source is provided, provides fused mass in heap to be detained water source, and can effectively suppress the surge pressure of containment.This cover system device layout is compact, takes up space little, arranges simple and easy, and economy is high.
To achieve these goals, technical scheme is as follows:
The passive core cooling system of Small reactor, it is characterised in that be arranged in containment, including:
Water supply tank, water supply tank is provided with connection pressure vessel in reactor coolant hot arc enter pipe and connection pressure vessel in cold section of reactor coolant go out pipe；
Peace water-filled pool, described peace water-filled pool arranges the peace note pipe of Bonding pressure container；
Remaining bank of heat exchangers, it is immersed in peace water-filled pool water, described remaining bank of heat exchangers is provided with connection reactor coolant hot arc enter pipe and cold section of reactor coolant of connection go out pipe, thus forming closed-loop path between remaining bank of heat exchangers and reactor coolant；
The shielding poind of the loop configuration being arranged on around pressure vessel, described shielding poind is enclosed construction, and shielding poind is provided with constrain pipeline and flowing line, and described constrain pipeline connects containment space and shield water pool inner water；Shield water pool inner water is stretched in described flowing line one end, and the other end stretches into the heap chamber that shielding poind is crowded around；It is provided with between described shielding poind and reactor coolant and connects the pressure relief pipeline of water body in reactor coolant hot arc and shielding poind, pressure relief pipeline sets valve group.
In a preferred embodiment of the invention, described water supply tank is high-pressure sealed water tank, and the inside stores full coolant water.
In a preferred embodiment of the invention, being provided with reflux pipe between cold section of shielding poind and reactor coolant, reflux pipe stretches into the one end contacted with water in shielding poind and is provided with filter screen.
In a preferred embodiment of the invention, flowing line is higher than the liquid level of shielding poind in the exit position in heap chamber.
In a preferred embodiment of the invention, the pool wall of described shielding poind and cover plate are shielding steel plate, be provided with separation steel plate, separation steel plate is provided with fluid connection gap in shielding poind.
In a preferred embodiment of the invention, described containment inwall is provided with condensing hot air furnace gathering sill.
For the problems referred to above, the present invention provides the passive core cooling system of a kind of Small reactor, Safety System Design suitable in small-sized safety shell, realize under accident, taking away reactor core decay heat, peace water filling source is provided, provides fused mass in heap to be detained water source, and can effectively suppress the surge pressure of containment.This cover system device layout is compact, takes up space little, arranges simple and easy, and economy is high.
The feature of the present invention see graphic and better embodiment below the detailed description of this case and obtains and be well understood to.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the present invention.
Wherein, 1-pressure vessel；2-containment；3-water supply tank；4-water；5-enters pipe；6-goes out pipe；7-pacifies water-filled pool；8-water；9-peace note pipe；Bank of heat exchangers more than 10-；11-enters pipe；12-goes out pipe；13-shielding poind；14-water；The constrain pipeline of 15-；16-flowing line；17-pressure relief pipeline；18-valve group；19-filter screen；20-reflux pipe；21-condensing hot air furnace gathering sill；22-piles chamber.
Detailed description of the invention
For the technological means making the present invention realize, creation characteristic, reach purpose and effect and be easy to understand, the present invention is expanded on further below in conjunction with specific embodiment.
Referring to Fig. 1, the passive core cooling system of Small reactor, including:
Water supply tank 3, water supply tank is high-pressure sealed water tank, and the inside stores full coolant water.The top of water supply tank 3 be provided with connection pressure vessel in reactor coolant hot arc enter pipe 5, bottom be provided with connection pressure vessel in cold section of reactor coolant go out pipe 6；
Peace water-filled pool 7, peace water-filled pool is a normal pressure open water pool, and the inside contains the water of certain liquid level；Peace water-filled pool arranges the peace note pipe 9 of Bonding pressure container；
Remaining bank of heat exchangers 10, its entirety is immersed in peace water-filled pool water, what the top of remaining bank of heat exchangers was provided with connection reactor coolant hot arc enters pipe 11, what bottom was provided with cold section of reactor coolant of connection goes out pipe 12, thus remaining bank of heat exchangers 10, enter pipe 11, go out the hot arc of pipe 12 and coolant and cold section form a closed-loop path；
The shielding poind 13 of the loop configuration being arranged on around pressure vessel, shielding poind is the airtight pond of a steel construction, the water (shield water) of the certain liquid level of interior storage.Shielding poind is provided with constrain pipeline 15, flowing line 16.Constrain pipeline 15 connects water body in containment space and shielding poind；Water body in shielding poind is stretched in flowing line 16 one end, and the other end stretches into the heap chamber that shielding poind is crowded around；Flowing line is higher than the liquid level of shielding poind in the exit position in heap chamber.It is provided with the pressure relief pipeline 17 connecting reactor coolant hot arc and shield water pool inner water between shielding poind with reactor coolant hot arc, pressure relief pipeline 17 sets valve group 18.
Being provided with reflux pipe 20 between cold section of shielding poind and reactor coolant, reflux pipe stretches into the one end contacted with water in shielding poind and is provided with filter screen 19.
It addition, containment inwall is provided with condensing hot air furnace gathering sill 21.
It is arranged in the reactor in containment 2 when there is the LOCA accident of such as pipeline breaking, high energy steam is spurted in containment 2, without any constrain measure, in containment 2, pressure can raise rapidly, there is containment 2 superpressure or the probability of penetration piece seal failure.In the present invention, high energy steam is entered in the water 14 (shield water) of shielding poind 13 by constrain pipeline 15 and flowing line 16, carries out condensation heat release, thus suppressing pressure rapid increase in containment 2.(therefore the water level of the water 14 in shielding poind 13 can not be significantly high, will reserve enough spaces and hold the non-condensable gas entered by constrain pipeline 15 and flowing line 16.)
There is early stage in LOCA accident, reactor core pressure is significantly high, and now the respective valves gone out on pipe 6 of water supply tank 3 is opened, and in water supply tank, the water 4 of 3 utilizes gravity head to pass through pipe 6 piii reactor, it is provided that a certain amount of high-pressure safety injection water source.Water supply tank 3 enter pipe 5 for balancing pressure.
Along with the valve group 18 continued on development or pressure relief pipeline 17 of LOCA accident is opened, reactor core pressure is gradually lowered, and the pressure in containment 2 slowly raises, when both reach to balance, the water 8 of peace water-filled pool 7 utilizes gravity head to pass through peace note pipe 9 piii reactor, it is provided that a certain amount of low pressure peace water filling source.
Afterwards, the high-temperature steam in containment 2 condenses (being realized by containment cooling system, non-invention content) at the inwall of containment 2, and condensed water is imported in peace water-filled pool by condensing hot air furnace gathering sill 21, gives peace water-filled pool make-up water source.
The function of pressure relief pipeline 17 is controllably by reactor coolant discharge to the water 14 of shielding poind 13, is typically under LOCA accident and uses.After the valve group 18 on pressure relief pipeline 17 is opened, reactor coolant just runs in the water 14 of shielding poind 13, with water 14 combination cooling.While reducing coolant pressure, the liquid level of water 14 is made to raise.When the liquid level of water 14 is higher than the exit position of flowing line 16, water 14 spills in heap chamber 22 by flowing line 16, by pressure vessel 1 submergence gradually (another cools down the mode of reactor core, and piles the interior means being detained as fused mass).In LOCA accident for a long time, along with coolant is constantly flowed out by break location and constrain pipeline 17, in heap chamber 22, the water level of submergence pressure vessel 1 is more and more higher, finally have enough gravity heads, water in heap chamber 22 is pressed in pressure vessel 1 by filter screen 19 and reflux pipe 20, it is achieved long-term circulating cooling.
And be placed in the remaining bank of heat exchangers 10 in peace water-filled pool 7 and enter pipe 11 and go out pipe 12 and mainly work when non-LOCA accident, reactor core decay heat is discharged in the water 8 pacifying water-filled pool 7 by pipeline and heat exchanger.Specifically, when there is non-LOCA accident, the respective valves gone out on pipe 12 of remaining bank of heat exchangers 10 is opened, thus remaining bank of heat exchangers 10, enter pipe 11, go out the hot arc of pipe 12 and coolant and cold section form a closed-loop path, this loop utilizes Natural Circulation power far to turn, and is brought into from reactor core by heat the water 8 of peace water-filled pool 7.
Now peace water-filled pool 7 is an intermediate heat trap, and it can absorb a certain amount of reactor core decay heat brought by remaining bank of heat exchangers 10 and pipeline thereof, but when the water saturation of the inside, and after being evaporated to containment 2, its heat absorption function will reduce.Water 8 volume in peace water-filled pool 7 is now rationally set on the one hand, to pass through condensing hot air furnace gathering sill 21 on the other hand in time by the condensing hot air furnace of containment 2 inwall to peace water-filled pool 7.The specific implementation of condensing hot air furnace repeats no more herein.
The ultimate principle of the present invention, principal character and advantages of the present invention have more than been shown and described.Skilled person will appreciate that of the industry; the present invention is not restricted to the described embodiments; simply principles of the invention described in above-described embodiment and description; the present invention also has various changes and modifications without departing from the spirit and scope of the present invention, and these changes and improvements both fall within claimed the scope of the present invention.The protection domain of application claims is defined by appending claims and equivalent thereof.
Claims (6)
1. the passive core cooling system of Small reactor, it is characterised in that be arranged in containment, including:
Water supply tank, water supply tank is provided with connection pressure vessel in reactor coolant hot arc enter pipe and connection pressure vessel in cold section of reactor coolant go out pipe；
Peace water-filled pool, described peace water-filled pool arranges the peace note pipe of Bonding pressure container；
Remaining bank of heat exchangers, it is immersed in peace water-filled pool water, described remaining bank of heat exchangers is provided with connection reactor coolant hot arc enter pipe and cold section of reactor coolant of connection go out pipe, thus forming closed-loop path between remaining bank of heat exchangers and reactor coolant；
The shielding poind of the loop configuration being arranged on around pressure vessel, described shielding poind is enclosed construction, and shielding poind is provided with constrain pipeline and flowing line, and described constrain pipeline connects containment space and shield water pool inner water；Shield water pool inner water is stretched in described flowing line one end, and the other end stretches into the heap chamber that shielding poind is crowded around；It is provided with between described shielding poind and reactor coolant and connects the pressure relief pipeline of water body in reactor coolant hot arc and shielding poind, pressure relief pipeline sets valve group.
2. the passive core cooling system of Small reactor according to claim 1, it is characterised in that described water supply tank is high-pressure sealed water tank, the inside stores full coolant water.
3. the passive core cooling system of Small reactor according to claim 1, it is characterised in that be provided with reflux pipe between cold section of shielding poind and reactor coolant, reflux pipe stretches into the one end contacted with water in shielding poind and is provided with filter screen.
4. the passive core cooling system of Small reactor according to claim 1, it is characterised in that flowing line is higher than the liquid level of shielding poind in the exit position in heap chamber.
5. the passive core cooling system of Small reactor according to claim 1, it is characterised in that the pool wall of described shielding poind and cover plate are shielding steel plate, is provided with separation steel plate, separation steel plate is provided with fluid connection gap in shielding poind.
6. the passive core cooling system of Small reactor according to claim 1, it is characterised in that be provided with condensing hot air furnace gathering sill on described containment inwall.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410719385.7A CN105719706A (en) | 2014-12-01 | 2014-12-01 | Small reactor passive core cooling system |
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| CN201410719385.7A CN105719706A (en) | 2014-12-01 | 2014-12-01 | Small reactor passive core cooling system |
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Cited By (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105913883A (en) * | 2016-07-05 | 2016-08-31 | 中国核动力研究设计院 | Reactor passive core melt residual heat removal system and operation method |
| CN107799188A (en) * | 2017-10-30 | 2018-03-13 | 上海核工程研究设计院有限公司 | A kind of containment pressure supression system |
| CN108281204A (en) * | 2018-01-24 | 2018-07-13 | 中广核研究院有限公司 | A kind of small-sized heap peace note recirculating system |
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN108962408A (en) * | 2018-06-21 | 2018-12-07 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressure vessel cooling system based on vacuum chamber |
| CN109273125A (en) * | 2018-11-21 | 2019-01-25 | 中科瑞华（安徽）中子能源技术有限公司 | A kind of multifunctional light shielding construction of radiological unit |
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
| CN111710445A (en) * | 2020-06-10 | 2020-09-25 | 上海核工程研究设计院有限公司 | Safety facility configuration scheme for pressure vessel top double-layer shell design |
| CN112071451A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Pressurized water reactor multifunctional double-layer concrete containment system |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN112201372A (en) * | 2020-10-16 | 2021-01-08 | 上海核工程研究设计院有限公司 | Method for realizing retention of molten material in reactor core of nuclear reactor |
| CN112530611A (en) * | 2020-12-24 | 2021-03-19 | 上海核工程研究设计院有限公司 | Advanced and simplified small-pile passive special safety system |
| CN112923109A (en) * | 2021-03-22 | 2021-06-08 | 上海核工程研究设计院有限公司 | Safety relief valve door system |
| CN113035391A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting self-flow type air suction system |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
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Cited By (22)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105913883B (en) * | 2016-07-05 | 2017-12-15 | 中国核动力研究设计院 | The passive reactor core fused mass residual heat removal system of reactor and operation method |
| CN105913883A (en) * | 2016-07-05 | 2016-08-31 | 中国核动力研究设计院 | Reactor passive core melt residual heat removal system and operation method |
| CN107799188A (en) * | 2017-10-30 | 2018-03-13 | 上海核工程研究设计院有限公司 | A kind of containment pressure supression system |
| CN108281204A (en) * | 2018-01-24 | 2018-07-13 | 中广核研究院有限公司 | A kind of small-sized heap peace note recirculating system |
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN108962408A (en) * | 2018-06-21 | 2018-12-07 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressure vessel cooling system based on vacuum chamber |
| CN109346196B (en) * | 2018-11-13 | 2022-04-15 | 中国核动力研究设计院 | Active and passive cooling combined molten material in-pile retention system |
| CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
| CN109273125A (en) * | 2018-11-21 | 2019-01-25 | 中科瑞华（安徽）中子能源技术有限公司 | A kind of multifunctional light shielding construction of radiological unit |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
| CN111710445A (en) * | 2020-06-10 | 2020-09-25 | 上海核工程研究设计院有限公司 | Safety facility configuration scheme for pressure vessel top double-layer shell design |
| CN112071451A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Pressurized water reactor multifunctional double-layer concrete containment system |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN112071451B (en) * | 2020-09-15 | 2022-11-01 | 哈尔滨工程大学 | Multifunctional double-layer concrete containment system of pressurized water reactor |
| CN112201372A (en) * | 2020-10-16 | 2021-01-08 | 上海核工程研究设计院有限公司 | Method for realizing retention of molten material in reactor core of nuclear reactor |
| CN112201372B (en) * | 2020-10-16 | 2022-12-02 | 上海核工程研究设计院有限公司 | Method for realizing retention of molten material in reactor core of nuclear reactor |
| CN112530611A (en) * | 2020-12-24 | 2021-03-19 | 上海核工程研究设计院有限公司 | Advanced and simplified small-pile passive special safety system |
| CN113035391A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting self-flow type air suction system |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
| CN113140337B (en) * | 2021-03-05 | 2023-09-15 | 国科中子能(青岛)研究院有限公司 | Passive cooling system, method and reactor for multi-medium shared cooling channel |
| CN112923109A (en) * | 2021-03-22 | 2021-06-08 | 上海核工程研究设计院有限公司 | Safety relief valve door system |
| CN112923109B (en) * | 2021-03-22 | 2024-04-09 | 上海核工程研究设计院股份有限公司 | Safety pressure relief valve system |
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