CN109378096A - Reactor core refueling method for deep pool type low-temperature heat supply reactor - Google Patents
Reactor core refueling method for deep pool type low-temperature heat supply reactor Download PDFInfo
- Publication number
- CN109378096A CN109378096A CN201811342704.1A CN201811342704A CN109378096A CN 109378096 A CN109378096 A CN 109378096A CN 201811342704 A CN201811342704 A CN 201811342704A CN 109378096 A CN109378096 A CN 109378096A
- Authority
- CN
- China
- Prior art keywords
- hanging basket
- reactor
- pond
- pool
- control rod
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of reactors, and particularly relates to a reactor core refueling method of a deep pool type low-temperature heat supply reactor. Includes the step S1 of disassembling the drive assembly of the control rod drive mechanism; step S2, the upper hanging basket is disassembled section by section from top to bottom except the lowest section, and is moved into a water storage pool; step S3, the lowest section of the upper hanging basket and the middle hanging basket are detached and supported on the pool wall bracket of the water piling pool; step S4, connecting a material changing mechanism on an opening above the lower hanging basket through a material changing platform; step S5, opening the connecting gate; step S6, changing materials, and moving the spent fuel assembly into a spent fuel water pool; step S7, disconnecting the reloading platform and the lower hanging basket, withdrawing the reloading mechanism, and closing the connecting gate; step S8, mounting the lowest sections of the middle hanging basket and the upper hanging basket; step S9, sequentially moving the rest sections of the upper hanging basket from the storage pool to a water stacking pool, assembling and fixing; step S10, the control rod drive mechanism is installed inside the upper basket and the control rod assemblies are connected.
Description
Technical field
The invention belongs to nuclear reactor art fields, and in particular to a kind of reactor reloading pattern side of Deep Pool Low Temperature Heating Reactor
Method.
Background technique
For nuclear reactor according to the difference of coolant type, what China mainly applied sum includes presurized water reactor, heavy water reactor, boiling water
Heap, sodium-cooled fast reactor, high temperature gas cooled reactor etc.；According to the purpose classification of nuclear reactor, it is broadly divided into production heap, research reactor and power
Heap, swimming pool formula light-water reactor are currently used primarily in research neutrons characteristic, so to physics, biology, radiation protection and
Materialogy etc. is studied, mostly research reactor.Pressurized-water reactor nuclear power plant reactor fuel assemblies refueling, loading and unloading technique is all made of
Underwater overturning technique realizes transmission of the fuel assembly between reactor building and fuel plant.It is this reload technique and its
Set system complex, the time used of reloading is long, and the probability that fuel assembly lifting accident occurs is higher, threatens nuclear safety
It is very big；And the general water of swimming VVR type reactor applied of China is shallower at present, and only 10 meters or so, structure in fuel assembly and heap
Part is generally relatively simple, can directly utilize dedicated long handle tool grabbing assembly, is transported to and heap water by transferring barrel and inclined channel
In the Spent Fuel Pool that pond is communicated by gate.But the low temperature heating reactor of deep water pond type is then neither identical as above-mentioned the two, more than 20
The pond of rice, is influenced by pool inner water stream, and long handle tool completes the crawl work of component without enough rigidity under water, together
When pond inner member it is also complex, need to dismantle different shape, size, the pond inner member of weight and control rod drive mechanism, heap
Core could complete refueling operation towards refueling agency.The distinctive reator body structure of Deep Pool Low Temperature Heating Reactor and deep water characteristic,
It needs to study dedicated reactor reloading pattern technique and is just able to satisfy requirement of reloading, complete work of reloading.
Summary of the invention
The purpose of the present invention is establishing on the basis of Deep Pool Low Temperature Heating Reactor design feature, a kind of reactor core is provided and is changed
The method for expecting process flow, reloading, process flow is simple, the time of reloading is shorter, safe and reliable, which only refers to reactor core
Process of reloading, do not include the receiving, inspection and storage of novel fuel assembly.
To achieve the above objectives, the technical solution adopted by the present invention is that a kind of reactor reloading pattern of Deep Pool Low Temperature Heating Reactor
Method, the Deep Pool Low Temperature Heating Reactor include the heap pond being arranged in reactor hall, are arranged in the heap pool bottom
The reactor core in portion；It further include the upper hanging basket, middle hanging basket, lower hanging basket from top to bottom set gradually；Control rod is equipped in the upper hanging basket
Driving mechanism is equipped with control rod guide tubes and bundles in the middle hanging basket, and the reactor core is arranged in the lower hanging basket, and the lower hanging basket is logical
It crosses reactor core pedestal to be arranged and further includes the pond cover board being arranged in heap sink top opening in the heap basin bottom and set
Set the thermal insulation board below the pond cover board；The upper hanging basket is segmented multilayered structure, lifting can be layered, in every layer of company
Mating surface is connect equipped with seismic support, folding para-seismic support；The pool wall in the heap pond is equipped with pool wall bracket；Also wrap
The Spent Fuel Pool being connected to by connecting gate with the heap pond is included, the Spent Fuel Pool is equipped with spentnuclear fuel and keeps in screen work；
It further include saving pond；The reactor reloading pattern method, wherein include the following steps:
Step S1 disengages the control rod drive mechanism and the C&P systems, by the control rod drive mechanism
Driving assembly dismantles simultaneously integral hoisting to the reactor hall designated position；
The upper hanging basket is from top to bottom dismantled paragraph by paragraph in addition to lowermost, is moved to from the reactor hall by step S2
In the preservation pond；
The lowermost of the upper hanging basket and the middle hanging basket are removed and are supported on the pond in the heap pond by step S3
On wall bracket, expose the reactor core equipped with fuel assembly in the lower hanging basket；
The refueling agency for being used to replace the fuel assembly is connected to the lower hanging basket by the platform that reloads by step S4
In side's opening, two secondary roots are carried out；
Step S5 opens the connection gate；
Step S6 is changed by the refueling agency according to the subregion of the fuel assembly according to burnup calculated result
Material keeps in screen work the spentnuclear fuel that the irradiated fuel assembly for novel fuel assembly moves in the Spent Fuel Pool is needed replacing
On；
Step S7, the connection of reload after reloading, described in disconnection platform and the lower hanging basket, withdraws the refueling machine
Structure closes the connection gate；
The middle hanging basket is taken from the pool wall bracket and is installed on the lower hanging basket upper opening by step S8；By institute
The lowermost for stating hanging basket is taken from the pool wall bracket to be installed on the middle hanging basket；
Step S9 successively moves to remaining each segmentation of the upper hanging basket in the heap pond simultaneously from the preservation pond
Assembling is fixed；
The driving component of the control rod drive mechanism and driving line are installed to the upper hanging basket by step S10
Upper end and inside connect the control rod drive mechanism and the C&P systems.
Further, in the step S1, by the disassembly of the driving assembly of control rod drive mechanism and integral hoisting is to described
Behind reactor hall designated position, further includes successively dismantling the pond cover board and the thermal insulation board, moved to from the heap pond
In the preservation pond.
Further, in the step S9 further include: be coupled the antidetonation branch during the upper hanging basket assembling
Frame.
It further, further include that the thermal insulation board is installed, then by institute after installing the para-seismic support in the step S9
Pond cover board is stated to bind.
Further, in the step S3, wherein the lowermost of the basket of hanging oneself is supported on the lower branch of the pool wall bracket
On frame, the middle hanging basket is supported on the upper bracket of the pool wall bracket.
The beneficial effects of the present invention are:
Compared to the reactor reloading pattern method of existing swimming-pool reactor, reactor reloading pattern method provided by the present invention is not required to
The underwater overturning of irradiated fuel assembly is carried out, underwater tipper, component refueling machine and elevator, component relaying transport can be saved
A large amount of special equipments such as bucket, nuclear fuel transhipment pond, and refueling operation process flow is simple, the safe and reliable, time is not grown；It can
The efficiency of reloading for improving nuclear reactor, reduces the cost of refuelling system and the labor intensity of operator, improves the warp of reactor
Ji property.
Detailed description of the invention
Fig. 1 is schematic diagram (the reactor reloading pattern behaviour of Deep Pool Low Temperature Heating Reactor described in the specific embodiment of the invention
Before work)；
Fig. 2 is the showing in core recharge operation of Deep Pool Low Temperature Heating Reactor described in the specific embodiment of the invention
It is intended to and (in figure, on the pool wall in heap pond 5, is located at the lowermost that " upper hanging basket 6 " below " middle hanging basket 4 " is upper hanging basket 6)；
In figure: 1- reactor core pedestal, 2- reactor core, hanging basket under 3-, hanging basket in 4-, 5- heap pond, the upper hanging basket of 6-, 7- antidetonation branch
Frame, 8- thermal insulation board, the pond 9- cover board, 10- control rod drive mechanism, 11- connection gate, 12- reload platform, 13- spentnuclear fuel water
Pond, 14- spentnuclear fuel keep in screen work, and 15- saves pond, 16- boom hoisting, 17- refueling agency.
Specific embodiment
The invention will be further described with reference to the accompanying drawings and examples.
The reactor reloading pattern method of a kind of Deep Pool Low Temperature Heating Reactor provided by the invention, as shown in Figure 1, deep water pond type is low
Warm process heat reactor includes the heap pond 5 being arranged in reactor hall, and the reactor core 2 of 5 bottom of heap pond is arranged in；Further include by up to
Under the upper hanging basket 6, middle hanging basket 4, the lower hanging basket 3 that set gradually；It is equipped with control rod drive mechanism 10 in upper hanging basket 6, is set in middle hanging basket 4
There are control rod guide tubes and bundles, reactor core 2 is arranged in lower hanging basket 3, and lower hanging basket 3 is arranged in 5 bottom of heap pond, also by reactor core pedestal 1
Including the pond cover board 9 being arranged in 5 top opening of heap pond and the thermal insulation board 8 being arranged in below pond cover board 9；Upper hanging basket 6
For segmented multilayered structure, it can be layered lifting, mating surface is connected at every layer equipped with seismic support, folding antidetonation branch
Frame 7；The pool wall in heap pond 5 is equipped with pool wall bracket；It further include the Spent Fuel Pool being connected to by connecting gate 11 with heap pond 5
13, Spent Fuel Pool 13 is equipped with spentnuclear fuel and keeps in screen work 14；It further include saving pond 15.
Reactor reloading pattern method provided by the present invention, includes the following steps:
Step S1 when reloading, disengages control rod drive mechanism 10 and C&P systems first, utilizes dedicated extracting tool
The driving assembly of control rod drive mechanism 10 is dismantled, then integral hoisting is then successively torn open to reactor hall designated position
Pond cover board 9 and thermal insulation board 8 are moved to from heap pond 5 and are saved in pond 15 by boiled water pond cover board 9 and thermal insulation board 8；
Step S2 from top to bottom dismantles upper hanging basket 6 paragraph by paragraph in addition to lowermost, moves to from heap pond 5 and saves pond 15
Interior, para-seismic support 7 is accordion structure, does not influence the disassembly of hanging basket 6；
Step S3, it is contemplated that during reactor operation, the lowermost and middle hanging basket 4 of upper hanging basket 6 are by the dosage radiated
It is larger, it should not be passed in and out from reactor hall, therefore the lowermost of upper hanging basket 6 and middle hanging basket 4 are removed and are temporarily supported above heap water
On the pool wall bracket in pond 5, expose the reactor core 2 equipped with fuel assembly in lower hanging basket 3；Wherein the lowermost of upper hanging basket 6 is supported on
On the lower bracket of pool wall bracket, middle hanging basket 4 is supported on the upper bracket of pool wall bracket；
The refueling agency 17 for being used for refuelling component is connected to lower 3 top of hanging basket by the platform 12 that reloads by step S4
In opening；At this point, 2 component of reactor core is perfectly facing top, work of reloading can be started, common fuel assembly deeper in view of pond
Gripping tool rigidity cannot be met the requirements, therefore be provided in the upper flange surface of lower hanging basket 3 and connect with what the platform 12 that reloads matched
Mouthful, the platform 12 that reloads is used for two secondary roots of refueling agency 17, guarantees that gripping tool possesses the rigidity having enough, meets crawl and wants
It asks；
Step S5 opens the connection gate 11 between heap pond 5 and Spent Fuel Pool 13；
Step S6 is reloaded by refueling agency 17 according to the subregion of fuel assembly according to burnup calculated result, need
The irradiated fuel assembly for being changed to novel fuel assembly moves to the spentnuclear fuel in Spent Fuel Pool 13 and keeps in (spentnuclear fuel group on screen work 14
Part be burnt in reactor, used fuel assembly)；Overall process of reloading is completed under water；
Step S7 after reloading, disconnects the connection of reload platform 12 and lower hanging basket 3, withdraws refueling agency 17, the company of closing
Connect gate 11；
Middle hanging basket 4 is taken from pool wall bracket and is installed on lower 3 upper opening of hanging basket by step S8；By the most lower of upper hanging basket 6
Section is taken from pool wall bracket to be installed on middle hanging basket 4；
Remaining each segmentation of upper hanging basket 6 is successively moved in the heap pond 5 and is assembled from preservation pond 15 by step S9
It is fixed, it has been coupled para-seismic support 7 during the assembling of upper hanging basket 6, has been subsequently mounted thermal insulation board 8, then pond cover board 9 is bound；
The driving assembly of control rod drive mechanism 10 and driving line are installed to the upper end of upper hanging basket 6 and interior by step S10
Portion connects control rod drive mechanism 10 and C&P systems, completes to reload.
Method 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 (5)
1. a kind of reactor reloading pattern method of Deep Pool Low Temperature Heating Reactor, the Deep Pool Low Temperature Heating Reactor, using control rod
The heap in heap pond (5) bottom is arranged including the heap pond (5) being arranged in reactor hall in component control reactivity
Core (2)；It further include the upper hanging basket (6), middle hanging basket (4), lower hanging basket (3) from top to bottom set gradually；It is set in the upper hanging basket (6)
Have a driving line of control rod drive mechanism (10), the control rod drive mechanism (10) for the C&P systems promotion and
Decline, control rod guide tubes and bundles is equipped in the middle hanging basket (4), reactor core (2) setting is in the lower hanging basket (3), under described
Hanging basket (3) setting further includes being arranged in the heap pond above the reactor core pedestal (1) for being fixed on heap pond (5) bottom
(5) the pond cover board (9) in top opening and the thermal insulation board (8) being arranged below the pond cover board (9)；The upper hanging basket
(6) it is segmented multilayered structure, lifting can be layered, mating surface is connected at every layer equipped with seismic support, folding anti-
It shakes bracket (7)；The pool wall of the heap pond (5) is equipped with pool wall bracket；It further include by connection gate (11) and the heap water
The Spent Fuel Pool (13) of pond (5) connection, the Spent Fuel Pool (13) are equipped with spentnuclear fuel and keep in screen work (14)；It further include saving
Pond (15)；The reactor reloading pattern method, characterized in that include the following steps:
Step S1 disengages the control rod drive mechanism (10) and the C&P systems, by the control rod drive mechanism
(10) driving assembly dismantles simultaneously integral hoisting to the reactor hall designated position；
The upper hanging basket (6) is from top to bottom dismantled paragraph by paragraph in addition to lowermost, moves to institute from the reactor hall by step S2
It states and saves in pond (15)；
The lowermost of the upper hanging basket (6) and the middle hanging basket (4) are removed and are supported on the heap pond (5) by step S3
On the pool wall bracket, expose the reactor core (2) equipped with fuel assembly in the lower hanging basket (3)；
Step S4, by the refueling agency (17) for being used to replace the fuel assembly by the platform that reloads (12) be connected to it is described under hang
On basket (3) upper opening, two secondary roots are carried out；
Step S5 opens the connection gate (11)；
Step S6 is changed by the refueling agency (17) according to the subregion of the fuel assembly according to burnup calculated result
Material, needing replacing, the spentnuclear fuel that the irradiated fuel assembly for novel fuel assembly moves in the Spent Fuel Pool (13) is temporary
On screen work (14)；
Step S7, the connection of reload after reloading, described in disconnection platform (12) and the lower hanging basket (3) are reloaded described in withdrawal
Mechanism (17) closes the connection gate (11)；
The middle hanging basket (4) is taken from the pool wall bracket and is installed on lower hanging basket (3) upper opening by step S8；It will
The lowermost of the upper hanging basket (6) is taken from the pool wall bracket to be installed on the middle hanging basket (4)；
Remaining each segmentation of the upper hanging basket (6) is successively moved to the heap pond from the preservation pond (15) by step S9
(5) in and fixation is assembled；
The driving component of the control rod drive mechanism (10) and driving line are installed to the upper hanging basket (6) by step S10
Upper end and inside, connect the control rod drive mechanism (10) and the C&P systems.
2. reactor reloading pattern method as described in claim 1, it is characterized in that: in the step S1, by control rod drive mechanism
It (10) further include successively dismantling the pond after driving assembly disassembly and integral hoisting to the reactor hall designated position
Cover board (9) and the thermal insulation board (8) move in the preservation pond (15) from the heap pond (5).
3. reactor reloading pattern method as described in claim 1, it is characterized in that: in the step S9 further include: hang oneself described
Basket (6) has been coupled the para-seismic support (7) during assembling.
4. reactor reloading pattern method as claimed in claim 3, it is characterized in that: installing the antidetonation branch in the step S9
It further include installing the thermal insulation board (8), then the pond cover board (9) is bound after frame (7).
5. reactor reloading pattern method as described in claim 1, it is characterized in that: in the step S3, wherein described hang oneself basket (6)
Lowermost be supported on the lower bracket of the pool wall bracket, the middle hanging basket (4) is supported on the upper bracket of the pool wall bracket
On.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811342704.1A CN109378096B (en) | 2018-11-12 | 2018-11-12 | Reactor core refueling method for deep pool type low-temperature heat supply reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811342704.1A CN109378096B (en) | 2018-11-12 | 2018-11-12 | Reactor core refueling method for deep pool type low-temperature heat supply reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109378096A true CN109378096A (en) | 2019-02-22 |
| CN109378096B CN109378096B (en) | 2020-06-23 |
Family
ID=65384374
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811342704.1A Active CN109378096B (en) | 2018-11-12 | 2018-11-12 | Reactor core refueling method for deep pool type low-temperature heat supply reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109378096B (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111667935A (en) * | 2020-06-19 | 2020-09-15 | 中国核动力研究设计院 | Integral dismounting device for inversion type driving mechanism of nuclear reactor |
| CN111724923A (en) * | 2020-06-23 | 2020-09-29 | 中国原子能科学研究院 | Support system, support device and reactor refueling method |
| CN112037942A (en) * | 2020-09-08 | 2020-12-04 | 中国原子能科学研究院 | Cover plate device and pool type reactor with same |
| CN112699433A (en) * | 2020-11-16 | 2021-04-23 | 西南交通大学 | Method for classifying nuclear reactor fuel assembly seismic analysis mold building structure types |
| CN112836269A (en) * | 2020-11-16 | 2021-05-25 | 西南交通大学 | Method for splicing nuclear reactor fuel assembly anti-seismic analysis modeling substructure types |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5069863A (en) * | 1989-07-10 | 1991-12-03 | Westinghouse Electric Corp. | Dual winch nuclear fuel transfer system providing more reliable fuel transfer during refueling operations |
| CN1385861A (en) * | 2002-06-19 | 2002-12-18 | 北京北大青鸟有限责任公司 | Deep water tank nuclear heat supply reactor adopting waste fuel of nuclear power station |
| RU2348084C1 (en) * | 2007-08-17 | 2009-02-27 | Федеральное государственное унитарное предприятие "Всероссийский научно-иследовательский институт неорганических материалов имени академика А.А. Бочвара" | Device for withdrawal of spent fuel assemblies |
| CN103000237A (en) * | 2011-08-19 | 2013-03-27 | 巴布科克和威尔科克斯核能股份有限公司 | Nuclear reactor refueling methods and apparatuses |
| US20130301784A1 (en) * | 2012-04-17 | 2013-11-14 | Babcock & Wilcox Mpower, Inc. | Suspended upper internals for compact nuclear reactor including a lower hanger plate |
-
2018
- 2018-11-12 CN CN201811342704.1A patent/CN109378096B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5069863A (en) * | 1989-07-10 | 1991-12-03 | Westinghouse Electric Corp. | Dual winch nuclear fuel transfer system providing more reliable fuel transfer during refueling operations |
| CN1385861A (en) * | 2002-06-19 | 2002-12-18 | 北京北大青鸟有限责任公司 | Deep water tank nuclear heat supply reactor adopting waste fuel of nuclear power station |
| RU2348084C1 (en) * | 2007-08-17 | 2009-02-27 | Федеральное государственное унитарное предприятие "Всероссийский научно-иследовательский институт неорганических материалов имени академика А.А. Бочвара" | Device for withdrawal of spent fuel assemblies |
| CN103000237A (en) * | 2011-08-19 | 2013-03-27 | 巴布科克和威尔科克斯核能股份有限公司 | Nuclear reactor refueling methods and apparatuses |
| US20180277270A1 (en) * | 2011-08-19 | 2018-09-27 | Bwxt Mpower, Inc. | Nuclear reactor refueling methods and apparatuses |
| US20130301784A1 (en) * | 2012-04-17 | 2013-11-14 | Babcock & Wilcox Mpower, Inc. | Suspended upper internals for compact nuclear reactor including a lower hanger plate |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111667935A (en) * | 2020-06-19 | 2020-09-15 | 中国核动力研究设计院 | Integral dismounting device for inversion type driving mechanism of nuclear reactor |
| CN111724923A (en) * | 2020-06-23 | 2020-09-29 | 中国原子能科学研究院 | Support system, support device and reactor refueling method |
| CN111724923B (en) * | 2020-06-23 | 2022-10-28 | 中国原子能科学研究院 | Support system, support device and reactor refueling method |
| CN112037942A (en) * | 2020-09-08 | 2020-12-04 | 中国原子能科学研究院 | Cover plate device and pool type reactor with same |
| CN112037942B (en) * | 2020-09-08 | 2023-05-23 | 中国原子能科学研究院 | Cover plate device and pool type reactor with same |
| CN112699433A (en) * | 2020-11-16 | 2021-04-23 | 西南交通大学 | Method for classifying nuclear reactor fuel assembly seismic analysis mold building structure types |
| CN112836269A (en) * | 2020-11-16 | 2021-05-25 | 西南交通大学 | Method for splicing nuclear reactor fuel assembly anti-seismic analysis modeling substructure types |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109378096B (en) | 2020-06-23 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109378096A (en) | Reactor core refueling method for deep pool type low-temperature heat supply reactor | |
| US9865363B2 (en) | Nuclear fuel core, nuclear fuel cartridge, and methods of fueling and/or defueling a nuclear reactor | |
| TWI549138B (en) | Nuclear reactor ,pressurized water nuclear reactor and method for constructing a once-through steam generator used in the unclear reactor | |
| CN104919534B (en) | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel | |
| CN103000237A (en) | Nuclear reactor refueling methods and apparatuses | |
| CN109887628A (en) | A kind of weary pond of PWR nuclear power plant and refuelling pool integrated apparatus | |
| CN104272399A (en) | A method of refueling a nuclear reactor | |
| CN102842348A (en) | System and method for performing activation method radiation experiments in sodium-cooled fast reactor | |
| CN105097054A (en) | Integrated top cover applicable to pressurized water reactor nuclear power plant | |
| CN102708933B (en) | Spent fuel storage shaft shielding well lid and lifting device thereof | |
| TWI616894B (en) | Demolition method of nuclear power plant | |
| CN1323405C (en) | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor | |
| KR20150106450A (en) | Method and apparatus for the shielded relocation of a nuclear component | |
| CN209487163U (en) | The refuelling system of pool reactor | |
| CN110415853A (en) | Reprocessing plant irradiated fuel assembly stores and transports hanging basket | |
| US10923239B2 (en) | Moving an entire nuclear reactor core as a unitary structure | |
| WO2024061068A1 (en) | Reactor fuel-loading and refueling system and method | |
| CN104919533B (en) | nuclear fuel assembly handling device | |
| CN110010257B (en) | Device and method for assembling and disassembling strong radioactive core components of reactor of floating nuclear power station | |
| KR102495798B1 (en) | Control rod drive mechanism (CRDM) with remote disconnect mechanism | |
| CN104008785B (en) | A kind of metal mold spentnuclear fuel after-treatment device | |
| US20220230768A1 (en) | Pressure-containing silo for a pressurised water reactor nuclear power plant | |
| CN106297923A (en) | A kind of Spent Fuel Pool of pair of pond design | |
| EP0806778A1 (en) | Method and handling equipment for nuclear fuel handling | |
| JPH1054895A (en) | Fuel handling method and device |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20220519 Address after: 100031 12C, floor 12, building 4, yard 1, naoshikou street, Xicheng District, Beijing Patentee after: Zhonghe Yanlong Technology Co.,Ltd. Address before: No.1 courtyard, Sanqiang Road, Xinzhen, Fangshan District, Beijing Patentee before: CHINA INSTITUTE OF ATOMIC ENERGY |