CN109378089A - A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion - Google Patents
A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion Download PDFInfo
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- CN109378089A CN109378089A CN201811342702.2A CN201811342702A CN109378089A CN 109378089 A CN109378089 A CN 109378089A CN 201811342702 A CN201811342702 A CN 201811342702A CN 109378089 A CN109378089 A CN 109378089A
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- hanging basket
- reactor core
- reactor
- primary ioops
- pile component
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- 238000010438 heat treatment Methods 0.000 title claims abstract description 33
- 230000009182 swimming Effects 0.000 title claims abstract description 18
- 239000000446 fuel Substances 0.000 claims abstract description 18
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 claims abstract description 11
- 230000007246 mechanism Effects 0.000 claims abstract description 7
- 230000000903 blocking effect Effects 0.000 claims abstract description 3
- 230000008859 change Effects 0.000 claims abstract description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 16
- 230000009471 action Effects 0.000 claims description 3
- 230000013011 mating Effects 0.000 claims description 3
- 239000000284 extract Substances 0.000 claims description 2
- 238000000034 method Methods 0.000 abstract description 6
- 230000008569 process Effects 0.000 abstract description 5
- 230000009466 transformation Effects 0.000 abstract description 2
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 208000019901 Anxiety disease Diseases 0.000 description 1
- 230000036506 anxiety Effects 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000003344 environmental pollutant Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 231100000719 pollutant Toxicity 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/06—Means for locating or supporting fuel elements
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to swimming pool formula low temperature heating reactor technical fields, more particularly to a kind of in-pile component for swimming pool formula low temperature heating reactor power expansion, it is arranged in heap pond, including the lower hanging basket for being fixed on the reactor core pedestal of basin bottom, being arranged in above reactor core pedestal, middle hanging basket under detachable and replacement setting above hanging basket, detachable and replacement the upper hanging basket being arranged in above middle hanging basket;For the driving line of control rod drive mechanism to be arranged in upper hanging basket, for control rod guide tubes and bundles to be arranged in middle hanging basket, for reactor core to be arranged in lower hanging basket, reactor core can realize the change of power by adjusting the quantity of inner fuel component and simulated assembly, meet different power demands;It further include the primary Ioops system of several connection reactor cores and the blind plate for blocking primary Ioops system.The in-pile component can carry out the extension of reactor capability according to city heat supply demand, and structure is simple, be not necessarily to the extra transformation in circuit, not only shortened the period that process heat reactor comes into operation, but also greatly improve economy.
Description
Technical field
The invention belongs to swimming pool formula low temperature heating reactor technical fields, and in particular to one kind is used for swimming pool formula low temperature heating reactor function
The in-pile component of rate extension.
Background technique
Nuclear heating be it is a kind of by nuclear fission generate energy as heat source to surrounding cities central heating in the way of, with tradition
Heat source, which is compared, can substantially reduce disposal of pollutants, and heat supply is safe and reliable, will be effectively improved China's energy resource structure, alleviate increasingly tight
The energy supply anxiety situation of weight has protection environment, protection people's health and the coal-fired pressure of alleviation etc. positive
Meaning.
There are mainly three types of types for the low temperature heating reactor for designing and building at present: shell-type compression type, pool compression type and swimming
Pool type.First two heap-type design power is generally large, and thermal power reaches 200-600MW (megawatt), according to municipal heating systems load
It calculates, the process heat reactor of a 200MW can satisfy 100,000 family 100m2Three-bed room, be equivalent to 10,000,000 m2, can meet most of
Big, medium-sized city, it is domestic it is many in, all there is an urgent need to low-temperature heat sources for small city and industrial area, but often because of its heat supply network scale
Less, the nuclear heat supplying pile gross investment of first two type is high, affects the economy of nuclear heating and the extension in market.And swimming pool
Formula low temperature heating reactor then can comprehensively consider its heat output of a reactor according to urban population, area of heat-supply service etc., design satisfaction not
With the reactor that scale city heat supply requires, under the premise of guaranteeing nuclear safety, low cost, investment are small, become nuclear heating
Mainstream.The consideration rate of China's urbanization till now is higher and higher, city size is also constantly expanding, the low temperature of a 200MW
Process heat reactor meets existing city heat supply requirement, but after city size expands, needs to create a low temperature heating reactor, economy meeting
It is multiplied and the original intention of nuclear heating itself is runed counter to, therefore, one kind being capable of appropriate extended power according to municipal heating systems demand
Low temperature heating reactor be necessary, and only swimming pool formula low temperature heating reactor has such extending space.
Summary of the invention
The object of the present invention is to provide a kind of in-pile components for swimming pool formula low temperature heating reactor, are guaranteeing reactor circuit
In the case that system configuration is constant, it is only necessary to which the extension for carrying out reactor core can improve the power of reactor, and then meet bigger
The demand of area of heat-supply service.
To achieve the above objectives, the technical solution adopted by the present invention is that a kind of be used for swimming pool formula low temperature heating reactor power expansion
In-pile component, be arranged in heap pond, wherein including be fixed on basin bottom reactor core pedestal, be arranged on reactor core pedestal
The lower hanging basket of side, detachable and replacement the middle hanging basket being arranged in above the lower hanging basket, detachable and replacement setting is in institute
State the upper hanging basket above hanging basket;For being arranged the driving line of control rod drive mechanism in the upper hanging basket, in the middle hanging basket
For control rod guide tubes and bundles to be arranged, it is used to that reactor core be arranged in the lower hanging basket, the reactor core can be by adjusting inner fuel group
The quantity of part and simulated assembly realizes the change of power, meets different power demands;It further include several connection reactor cores
Primary Ioops system and blind plate for blocking the primary Ioops system.
Further, the specification of the lower hanging basket is suitable for the reactor core of different capacity;According to the different function of the reactor core
The middle hanging basket and the upper hanging basket that rate replaces specification and the power is adapted.
Further, the primary Ioops system include in the heap pond, be connected to the delay tank of the reactor core be connected to
The outlet pipe of the delay tank;The delay is passed through by the water after the reactor core heating under the action of primary Ioops system
Tank enter the primary Ioops system, by the primary Ioops system primary Ioops main pump and primary Ioops heat exchanger heat exchange after, from
Water inlet pipe returns in the heap pond;The delay tank is used to postpone by the radgas in the water after reactor core heating
Decay.
Further, the primary Ioops system can separate the connection with the lower hanging basket by the blind plate.
Further, the upper hanging basket is segmented multilayered structure, can be layered lifting, in every layer of connection mating surface equipped with anti-
The para-seismic support for shaking support, meets shockproof requirements.
Further, the para-seismic support and the upper hanging basket, middle hanging basket are all made of the structure that can be dismantled under water.
Further, when needing to improve the power of the reactor core, after shutdown, the para-seismic support is removed, is removed former
The upper hanging basket and middle hanging basket having, extract the simulated assembly, are changed to fuel assembly, and replacement specification is suitable for the institute under higher power
The upper hanging basket and middle hanging basket of reactor core are stated, while removing all blind plates, is connected to all primary Ioops systems, to mention
The power of high swimming pool formula low temperature heating reactor increases area of heat-supply service.
The beneficial effects of the present invention are:
The extension of reactor capability can be carried out, structure is very simple, nothing according to city heat supply demand using the in-pile component
The extra transformation in circuit is needed, compared to the process heat reactor of newly-built one several hundred million grades of investments, which only needs replacement partial component can be real
The extension of existing reactor capability, investment budgey only millions, had not only shortened the period that process heat reactor comes into operation, but also greatly improve
Economy has boundless marketing and application space.
Detailed description of the invention
Fig. 1 is the in-pile component that swimming pool formula low temperature heating reactor power expansion is used for described in the specific embodiment of the invention
Schematic diagram in heap pond is set, includes the section of a branch in figure;
Fig. 2 is the swimming pool formula low temperature heating reactor system flow chart in the specific embodiment of the invention;
Fig. 3 is the floor plan of the reactor core in the specific embodiment of the invention;
In figure: 1- reactor core pedestal, 2- reactor core, hanging basket under 3-, hanging basket in 4-, 5- postpone tank, the upper hanging basket of 6-, 7- outlet pipe,
8- heap pond, 9- para-seismic support, 10- water inlet pipe, the pond 11- cover board, 12- control rod drive mechanism, 13- primary Ioops system, 14-
Primary Ioops main pump, 15- primary Ioops heat exchanger, 16- secondary circuit, 17- blind plate, 18- fuel assembly, 19- simulated assembly.
Specific embodiment
The invention will be further described with reference to the accompanying drawings and examples.
A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion provided by the invention is built upon swimmer's pool
On the basis of formula low temperature heating reactor design feature, which has the function of reactor core extension, and then improves reactor capability,
The case where meeting city heat supply changes in demand.
As shown in Figure 1 and Figure 2, a kind of in-pile component for swimming pool formula low temperature heating reactor power expansion provided by the invention,
Be arranged in heap pond 8 (8 upper opening of heap pond be equipped with pond cover board 11), including reactor core pedestal 1, lower hanging basket 3, middle hanging basket 4,
Postpone the parts such as tank 5, upper hanging basket 6, para-seismic support 9, blind plate 17.When normal operation, water enters heap by the runner of reactor core pedestal 1
In core 2, after the heat that reactor core 2 generates is taken out of, the primary Ioops main pump 14 by primary Ioops system 13 is evacuated in delay tank 5, is passed through
After radioactive decay delay, is entered in primary Ioops system 13 by outlet pipe 7, pass through the primary Ioops heat exchanger of primary Ioops system 13
15 transfer heat to secondary circuit 16, and heat exchanges heat with urban heating network again, after the transmitting for realizing heat, primary Ioops system
Coolant (water i.e. in primary Ioops system 13 after heat exchange) in system 13 again returns to heap pond 8 by water inlet pipe 10
In.
Lower hanging basket 3 is arranged by reactor core pedestal 1 in 8 bottom of heap pond, for being arranged reactor core 2 in lower hanging basket 3, reactor core 2 by
Fuel assembly 18 and associated component are constituted, and lower hanging basket 3 is used to fixed constraint and supporting fuel assemblies 18 and associated component, lower hanging basket
The reactor core 2 of different capacity demand, the i.e. fuel assembly 18 and simulated assembly 19 of different number can be set in 3.
Middle hanging basket 4 is removably arranged above lower hanging basket 3, for control rod guide tubes and bundles, middle hanging basket to be arranged in middle hanging basket 4
4 are also used to compress fuel assembly 18.
Upper hanging basket 6 is removably arranged above middle hanging basket 4;For control rod drive mechanism 12 to be arranged in upper hanging basket 6
Line is driven, control rod drive mechanism 12 uses wirerope rod withdrawal principle, and driving assembly is placed on the pond cover board 11 on heap top.On
Hanging basket 6 is segmented multilayered structure, can be layered lifting, connects the para-seismic support 9 that mating surface is equipped with seismic support at every layer,
Para-seismic support 9 plays the role of the seismic support of entire component, meets shockproof requirements.
According to heat demand, lower hanging basket 3, middle hanging basket 4 and upper hanging basket 6 select the specification for being suitable for different capacity demand, function
When rate needs to be promoted, no replacement is required for above-mentioned hanging basket.
As shown in Fig. 2, further including that (quantity of primary Ioops system 13 is 4 to several primary Ioops systems 13 in Fig. 2, only
The quantity of example, primary Ioops system 13 can be set according to reactor capability).One primary Ioops system 13 includes being located at heap pond 8
Interior, connection reactor core 2 delay tank 5, further includes the outlet pipe 7 of connection delay tank 5;Primary Ioops main pump in primary Ioops system 13
Water after being heated under the action of 14 by reactor core 2 is entered in primary Ioops system by delay tank 5;Postpone tank 5 for postponing by heap
The decay of the radgas in water after the heating of core 2, to reduce the equipment of primary Ioops system 13 and the dosage of technology room
It is horizontal;After water in primary Ioops system 13 completes heat exchange by primary Ioops heat exchanger 15, heap pond 8 is returned to by water inlet pipe 10
In.Return can separate the connection with lower hanging basket 3 by blind plate 17.
Fig. 3 is the floor plan of reactor core 2, by taking 200MW fuel assembly and 400MW fuel assembly as an example, initial designs heap
Lower hanging basket 3 in inner member carries out envelope according to the quantity for the fuel assembly 18 that can constrain and fix 400MW scale, wherein
Outer zone position uses 19 alternative fuel component 18 of simulated assembly, and meets core flow distribution and require, and specification is selected to be suitable for
(middle hanging basket 4 and upper hanging basket 6 then require to design the upper hanging basket 6 and middle hanging basket 4 of 200MW fuel assembly according to 200MW, with 400MW heap
Core arrangement is corresponding), correspond to the corresponding fuel assembly 18 of 200MW and control rod drive mechanism grid position, remaining component in heap pond 8
For 200MW and 400MW general (such as para-seismic support 9), being divided into 4 primary Ioops systems 13, (quantity of primary Ioops system is only to show
Example, the quantity of primary Ioops system can be set according to reactor capability).If initial heat demand is 200MW, by two therein
Primary Ioops system 13 is blocked using blind plate 17, and only two other primary Ioops system 13 participates in actual condition operation.When city is advised
Mould is gradually expanded, and heat demand improves, at this point, upper hanging basket 6 corresponding with 200MW reactor core display, middle hanging basket 4 are removed, by heap
Simulated assembly 19 in core 2 replaces with fuel assembly 18, reactor capability can be increased to 400MW, and selection specification is arranged
Suitable for the upper hanging basket 6 of 400MW fuel assembly and hanging basket 4 (upper hanging basket 6 namely corresponding with 400MW reactor core display and
Middle hanging basket 4), remaining the interior component of heap pond 8 remains unchanged, and opens all blind plates 17, at this point, 4 primary Ioops systems 13 are same
When participate in reactor reactor core 2 heat exchange, realize the extension of reactor capability, meet city heat supply demand.
Device of the present invention is not limited to embodiment described in specific embodiment, those skilled in the art according to
Technical solution of the present invention obtains other embodiments, also belongs to the scope of the technical innovation of the present invention.
Claims (7)
1. a kind of in-pile component for swimming pool formula low temperature heating reactor power expansion, setting is interior in heap pond (8), it is characterized in that:
Including being fixed on the reactor core pedestal (1) of basin bottom, the lower hanging basket (3) being arranged above reactor core pedestal (1), detachable and replacement
Middle hanging basket (4) of the setting above the lower hanging basket (3), detachable and replacement setting is above the middle hanging basket (4)
Upper hanging basket (6);For the driving line of control rod drive mechanism (12) to be arranged in the upper hanging basket (6), used in the middle hanging basket (4)
In for being arranged reactor core (2), the reactor core (2) can be by adjusting inside in setting control rod guide tubes and bundles, the lower hanging basket (3)
The quantity of fuel assembly (18) and simulated assembly (19) realizes the change of power, meets different power demands;It further include several
Item is connected to the primary Ioops system (13) of the reactor core (2) and the blind plate (17) for blocking the primary Ioops system (13).
2. in-pile component as described in claim 1, it is characterized in that: the specification of the lower hanging basket (3) is suitable for different capacity
The reactor core (2);The middle hanging basket (4) that specification is adapted with the power is replaced according to the different capacity of the reactor core (2)
With the upper hanging basket (6).
3. in-pile component as described in claim 1, it is characterized in that: the primary Ioops system (13) includes being located at the heap pond
(8) in, the delay tank (5) of the connection reactor core (2) and it is connected to the outlet pipe (7) for postponing tank (5);In the primary Ioops system
The primary Ioops system is entered by the delay tank (5) by the water after the reactor core (2) heating under the action of system (13)
(13), by the primary Ioops system (13) primary Ioops main pump (14) and primary Ioops heat exchanger (15) heat exchange after, from water inlet
(10) are managed to return in the heap pond (8);Delay tank (5) is used to postpone by the water after the reactor core (2) heating
The decay of radgas.
4. in-pile component as described in claim 1, it is characterized in that: the primary Ioops system (13) can pass through the blind plate
(17) separate the connection with the lower hanging basket (3).
5. in-pile component as described in claim 1, it is characterized in that: the upper hanging basket (6) is segmented multilayered structure, Neng Goufen
Layer lifting connects the para-seismic support (9) that mating surface is equipped with seismic support at every layer, meets shockproof requirements.
6. in-pile component as claimed in claim 5, it is characterized in that: the para-seismic support (9) and the upper hanging basket (6), in hang
Basket (4) is all made of the structure that can be dismantled under water.
7. in-pile component as claimed in claim 6, it is characterized in that: when needing to improve the power of the reactor core (2), in shutdown
Afterwards, the para-seismic support (9) are removed, remove original upper hanging basket (6) and middle hanging basket (4), extracts the simulated assembly (19),
Be changed to fuel assembly (18), replace the reactor core (2) of the specification under higher power upper hanging basket (6) and hanging basket (4),
All blind plates (17) are removed simultaneously, are connected to all primary Ioops systems (13), to improve swimming pool formula low temperature supplying
The power of thermal reactor increases area of heat-supply service.
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CN201811342702.2A CN109378089B (en) | 2018-11-12 | 2018-11-12 | Internal pile component for swimming pool type low-temperature heat supply pile power expansion |
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CN201811342702.2A CN109378089B (en) | 2018-11-12 | 2018-11-12 | Internal pile component for swimming pool type low-temperature heat supply pile power expansion |
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CN109378089A true CN109378089A (en) | 2019-02-22 |
CN109378089B CN109378089B (en) | 2024-07-02 |
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111508622A (en) * | 2020-04-28 | 2020-08-07 | 中国原子能科学研究院 | Reactor core and reactor |
Citations (17)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4246069A (en) * | 1977-07-05 | 1981-01-20 | Commissariat A L'energie Atomique | Heat-generating nuclear reactor |
CN85100044A (en) * | 1985-04-01 | 1985-09-10 | 清华大学 | Deepwater swimming-pool type reactor for supplying heat |
CH670724A5 (en) * | 1984-09-05 | 1989-06-30 | Georg Vecsey | Reactor with high neutron absorption temp. coefficient |
CN1039141A (en) * | 1989-08-24 | 1990-01-24 | 清华大学 | Forced-natural circulation bath-type heat-supplying reactor |
RU2070341C1 (en) * | 1994-02-24 | 1996-12-10 | Научно-исследовательский и конструкторский институт энерготехники | Pool reactor for heating nuclear plant |
CN1337719A (en) * | 2001-09-21 | 2002-02-27 | 田嘉夫 | Heat supplying nuclear reactor with forced-circulation cooling deep water including natural circulation |
US20050069074A1 (en) * | 2002-01-08 | 2005-03-31 | Yulun Li | Nuclear plant spent fuel low temperature reactor |
RU2010116244A (en) * | 2007-09-26 | 2011-11-10 | Дель Нова Вис С.Р.Л. (It) | NUCLEAR REACTOR, IN PARTICULAR, POOL TYPE WITH FUEL ELEMENTS OF NEW CONCEPT |
RU2497209C1 (en) * | 2012-07-24 | 2013-10-27 | Открытое Акционерное Общество "Ордена Ленина Научно-Исследовательский И Конструкторский Институт Энерготехники Имени Н.А. Доллежаля" | System for emergency cooldown of nuclear reactor of pond type |
CN104409114A (en) * | 2014-12-12 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Flow distribution device used for tank-type forced circulation reactor |
CN105023621A (en) * | 2015-06-12 | 2015-11-04 | 陈安海 | Fast reactor type coupling nuclear reaction implementation method and nuclear reactor for same |
CN105374408A (en) * | 2015-11-27 | 2016-03-02 | 田力 | Deep well type atmospheric pressure heat supply nuclear reactor |
CN205810388U (en) * | 2015-11-27 | 2016-12-14 | 新核(北京)能源科技有限公司 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
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 |
CN107945888A (en) * | 2016-08-25 | 2018-04-20 | 启迪新核(北京)能源科技有限公司 | Pool heat reactor and heat |
CN108682460A (en) * | 2018-05-23 | 2018-10-19 | 肖宏才 | Shallow pool nuclear energy low-temperature heat supply stack device and its operation method |
CN209216590U (en) * | 2018-11-12 | 2019-08-06 | 中国原子能科学研究院 | A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion |
-
2018
- 2018-11-12 CN CN201811342702.2A patent/CN109378089B/en active Active
Patent Citations (17)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4246069A (en) * | 1977-07-05 | 1981-01-20 | Commissariat A L'energie Atomique | Heat-generating nuclear reactor |
CH670724A5 (en) * | 1984-09-05 | 1989-06-30 | Georg Vecsey | Reactor with high neutron absorption temp. coefficient |
CN85100044A (en) * | 1985-04-01 | 1985-09-10 | 清华大学 | Deepwater swimming-pool type reactor for supplying heat |
CN1039141A (en) * | 1989-08-24 | 1990-01-24 | 清华大学 | Forced-natural circulation bath-type heat-supplying reactor |
RU2070341C1 (en) * | 1994-02-24 | 1996-12-10 | Научно-исследовательский и конструкторский институт энерготехники | Pool reactor for heating nuclear plant |
CN1337719A (en) * | 2001-09-21 | 2002-02-27 | 田嘉夫 | Heat supplying nuclear reactor with forced-circulation cooling deep water including natural circulation |
US20050069074A1 (en) * | 2002-01-08 | 2005-03-31 | Yulun Li | Nuclear plant spent fuel low temperature reactor |
RU2010116244A (en) * | 2007-09-26 | 2011-11-10 | Дель Нова Вис С.Р.Л. (It) | NUCLEAR REACTOR, IN PARTICULAR, POOL TYPE WITH FUEL ELEMENTS OF NEW CONCEPT |
RU2497209C1 (en) * | 2012-07-24 | 2013-10-27 | Открытое Акционерное Общество "Ордена Ленина Научно-Исследовательский И Конструкторский Институт Энерготехники Имени Н.А. Доллежаля" | System for emergency cooldown of nuclear reactor of pond type |
CN104409114A (en) * | 2014-12-12 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Flow distribution device used for tank-type forced circulation reactor |
CN105023621A (en) * | 2015-06-12 | 2015-11-04 | 陈安海 | Fast reactor type coupling nuclear reaction implementation method and nuclear reactor for same |
CN105374408A (en) * | 2015-11-27 | 2016-03-02 | 田力 | Deep well type atmospheric pressure heat supply nuclear reactor |
CN205810388U (en) * | 2015-11-27 | 2016-12-14 | 新核(北京)能源科技有限公司 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
CN107945888A (en) * | 2016-08-25 | 2018-04-20 | 启迪新核(北京)能源科技有限公司 | Pool heat reactor and heat |
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 |
CN108682460A (en) * | 2018-05-23 | 2018-10-19 | 肖宏才 | Shallow pool nuclear energy low-temperature heat supply stack device and its operation method |
CN209216590U (en) * | 2018-11-12 | 2019-08-06 | 中国原子能科学研究院 | A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion |
Non-Patent Citations (4)
Title |
---|
YXUAN ZHANG ET AL.: "Swimming pool-type low-temperature heating reactor:recent progress in research and application", ENERGY PROCEDIA, vol. 127, 30 September 2017 (2017-09-30), pages 425 - 431 * |
刘天才等: "中国先进研究堆安全设计", 《核动力工程》, vol. 2, 31 October 2006 (2006-10-31) * |
张亚东等: "49-2游泳池式反应堆低温供热演示验证", 中国原子能科学研究院年报, 30 June 2018 (2018-06-30), pages 50 - 52 * |
田嘉夫等: "200MW深水池6型供热堆(DPR-6)的方案设计", 核科学与工程, vol. 15, no. 03, 30 September 1995 (1995-09-30), pages 199 - 206 * |
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CN111508622A (en) * | 2020-04-28 | 2020-08-07 | 中国原子能科学研究院 | Reactor core and reactor |
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