CN110506310A - The container of storage and transport spent fuel - Google Patents
The container of storage and transport spent fuel Download PDFInfo
- Publication number
- CN110506310A CN110506310A CN201780089551.1A CN201780089551A CN110506310A CN 110506310 A CN110506310 A CN 110506310A CN 201780089551 A CN201780089551 A CN 201780089551A CN 110506310 A CN110506310 A CN 110506310A
- Authority
- CN
- China
- Prior art keywords
- container
- vessel
- fuel
- frame
- shell
- 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.)
- Pending
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
- G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
- G21F5/012—Fuel element racks in the containers
Abstract
The present invention relates to a kind of for storing and transporting the container of spent fuel, the container includes the main body formed by the vessel (1) of cylindrical steel, the vessel are closed in bottom, and it is equipped with the closed system of upper pin rope, the upper bolt closed system is equipped with leakage-preventing sealing device, to provide the structure reactance of container and the neutron shield to fuel, the vessel accommodate inner frame (4), the inner frame is formed by the grid of stainless steel sheet material (41), the grid defines multiple units (42), each unit is suitable for comprising pipe (5), the cross section for managing (5) is equal to the cross section of unit, the aluminium alloy guide part (43 with rectangle and triangular cross section is arranged around the unit (42), 44), its vessel (1) that decay heat is transmitted to steel from frame (4), outside vessel Side has heat-dissipation aluminum sectional material group (2), includes in the space between profile neutron shielding material (3).
Description
Goal of the invention
The purpose of the present invention is a kind of dual-purpose compact metal containers: storage and transport spent fuel.More specifically, this
Container is used in combination for managing to come with the spent fuel of the nuclear power station of pressurized water reactor (PWR) and boiling water reactor (BWR)
In these spent fuels can be transported to individual or centralized interim storage facility.
Background technique
Once being used for nuclear reactor, nuclear fuel will be stored in nuclear power station pond, so that the activity decay of fuel is simultaneously
It is allowed to cool.Then, spent fuel can be placed in dry warehouse, until the final stage of management is placed in storage container
Or in storage and shipping container (the latter is known as double-using container).Now, in Spain, high activity waste material is not transported, because its
It is saved in the pond or container in power station；But the creation of the temporary storage facilities due to centralization, it needs using suitable
Such waste material is transported the risk to new facility by double-using container, minimum from nuclear power plant.
These storage systems can ensure that secure storage and the element of transport spentnuclear fuel form by one group.Their purpose of design
Be to ensure that the set security function for requirement of abiding by the law: maintain material subcriticality and material it is closed, prevent its degradation；It removes
Outside other factors, this is by gamma ray and neutron irradiation shielding and by eliminating the residual heat that irradiated fuel generates come real
It is existing.
According to the type of nuclear fuel, fuel container in most cases can store 20 to 100 elements.Meet appearance
The spent fuel element of requirement (cooling time, burning and concentrating degree and other parameters) specified in device license can be according to warp
The loading plan for examining and ratifying is crossed to be stored.
Known dual-purpose canister is multilayer.In general, they are made of the cylindrical vessel with sealing closed system,
There is the anti-leak closed system sizable wall thickness to be made sometimes using lead layer with providing shielding for the radiation generated in it
It is shielded for special gamma radiation；Second wall is formed by neutron shield layer, and neutron shield layer is by outermost deceleration oxidant layer or has
Poisonous substance layer is realized.The outer surface of container is generally equipped with a series of fins made of copper, stainless steel or other metals, these fins
It is arranged in axially or radially position, to help to be cooled down by free convection, so that fuel covering temperature is lower than license pole
Limit.The center cavity of container is made of stainless steel or aluminium basket, including having determining boron content to control the component of Critical Degree, and is wrapped
Include the spent fuel element of quantification.Container is by double-canopy sealing, wherein innermost lid is steel and executes closed and screen
The function of covering, and outer cover executes structural intergrity maintenance function when the impact due to latent defect occurs.
It is some not only to be manufactured for store to be used to transport the containers of spent fuel again with single shell, with structure, closed
And function of shielding, mainly it is resistant to gamma radiation.
Summary of the invention
An object of the present invention designs and manufactures a series of maximum capacities, the dual-purpose appearance with economic competitiveness
Device, the container can accommodate PWR and BWR fuel, the active material of fuel additive, and can equip or can have assembly to rush
A possibility that hitting attenuator has improved positioning and better performance relative to the container used now.Double-using container has
Remove the optkmal characteristics for the residual heat that fuel element generates.
The container of the object of the invention includes:
The single wall carbon steel vessel for executing structure, limitation and function of shielding, mainly resist gamma radiation.The vessel have circle
Column construction, container top opening, is formed by circular cylindrical shell, is welded in bottom and is closed the vessel pedestal.Double bolted cover systems
System provides limitation and shielding.The system also allows easily to recycle fuel element under any normal or abnormal operating condition,
Meanwhile allowing the continuous pressure monitored between lid, to ensure and control any possible leakage of limitation barrier.
There is the frame made of stainless steel sheet material in the vessel of the steel, which defines grid,
For accommodating boron aluminum pipe wherein, fuel element is inserted again in the boron aluminum pipe, this makes the heat that can keep ensuring covering
The subcritical state and heating index of the limit.In the case where urgent of less demanding, boron aluminum pipe, boron can be replaced with boron aluminum sheet
Aluminum sheet forms the component part of the grid of frame by becoming.
The aluminum profile being radially disposed on the vessel to form the steel of container, facilitates in an entirely passive manner
The waste heat that dissipation fuel element generates, can remove the heat of generation.During packing material is inserted into these profiles and executes
Sub- radiation shield function.Outmost surface includes the metal wrapping part for the neutron shield.
At least two axle journals are protruded with hoisting container from inner vessel therein, and protrude two for moving the axle journal of container.
This structure allows in the ITSF (individually temporary storage facilities) in power plant or the CTSF in future (the interim storage of centralization is set
Apply) it is middle using identical container storage, and identical container is allowed to be used for multimodal transport (highway, railway or sea-freight), and nothing
It needs to reequip.For transport operation, what is desired is that the impact-attenuating device bolt that two are connected to container is fixed to container
The pallet for transporting itself that outer cover and bottom and protective barrier and container are placed on it.
The container has entirely autonomous design, does not need to share any system or component with nuclear power station during storage
(except pressure sensor, pressure sensor is mounted in outer cover, it is necessary to sampled-data system is connected to, between continuous monitoring lid
The pressure in space).
Frame is made of stainless steel structure (grid), the stainless steel structure by the thickness between 5 to 10 millimeters sheet material shape
At the sheet material forms unit, and insertion has square cross section in these units, with the thickness between 5 to 20 millimeters
Pipe or sheet material, the pipe or sheet material are by aluminium and boron carbide (Al-B with neutron absorption capability4C) parent metal category composite wood
Material (MMC) is made.The selection of the thickness of MMC pipe or sheet material is according to the design for being contained in spentnuclear fuel therein.Frame further through
Be fixed in the cavity of container by the guide part that aluminium section forms, aluminium section twist-on around the stainless steel structure of frame,
Decay heat is transmitted to the main body of container by the guide part from frame, in order to remove the heat from container.
It is removed by the decay heat that the fuel element accommodated in a reservoir generates by passive mode.It is not used and appoints in container
The coolant of what type, only internal cavity are pressurizeed with inertia helium atmosphere.Helium has thermal conductivity appropriate, helps to remove
Accommodate the decay heat of fuel in the frame.
The heat transfer mechanism considered in Vessel Design is described below in detail.
Fuel element is accommodated in the unit of frame, and under normal operating conditions, the fuel element is from container
Unique heat source.Heat is from UO2Particle is transmitted to the covering of element, then between being transmitted to occupy in container internal cavity therefrom
The helium of gap.Remaining element (sieve, nozzle, spring and conduit) for forming fuel element also distributes heat in inertia helium.
Other than with good Critical Control performance, MMC sheet material or pipe are also shown well due to its high aluminium content
Thermal conductivity.
The stainless steel sheet material of frame additionally aids heat dissipation, conducts heat to guide part by conduction.Finally, aluminum frame
The guide part of frame also contributes to removing heat from lower portion.Heat transmitting from the component group of frame to inner wall of utensil is to pass through biography
It leads and radiation mechanism generation.
The heat for reaching vessel interior surface is transmitted by the conduction of its thickness, is then inhaled again by aluminum profile and neutron
Receive device conduction, even up to neutron shield encapsulation piece.The encapsulation piece contains neutron shielding material.It is final in radial directions to move
Before heat, encapsulation piece is final transport element.It is envisaged that by heat sink section bar arrangement be placed on vessel and shell it
Between, the middle position between tangentially and radially, with the contact point of vessel or shell at, relative to radius or tangent line at about
45 ° of angle, to obtain optimal heat radiation.
In container bottom, heat is transmitted to outside through the conduction in by container bottom and in the axial direction from internal cavity
Surface.
In lid, heat also in axial direction in inner cover is transmitted to from fuel element by conduction, convection current and radiation.Phase
Same heat transfer mechanism is effective in space between the lid also to be pressurizeed with helium.
The heat and the heat by absorbing solar radiation that fuel element generates pass through convection current and radiation mechanism from container
Outer surface be transmitted in environment, these heats from the bottom of container are transmitted to storage facility substrate by conducting.
Detailed description of the invention
It is attached with one group in the present specification in order to supplement carried out description and in order to help to understand feature of the invention
Figure, depicts the following contents in the accompanying drawings in illustrative and not restrictive mode:
Fig. 1 shows the overall perspective of double-using container according to the present invention, wherein making various partial cross sections to observe
Its all component and its distribution.
Fig. 2 depicts the perspective view of vessel (1), and it illustrates partial cross section view, which forms the structure of container
Part.
Fig. 3 depicts the perspective view of the frame (4) of double-using container, shows the partial cross-section of the frame (4), wherein
In the cell structure for the frame that the insertion of MMC pipe is formed by stainless steel sheet material.
Fig. 4 depicts the perspective view of the frame of double-using container, and the partial cross-section of the frame (4) is also shown, wherein
MMC sheet material is fitted together with stainless steel sheet material, forms the cell structure of frame.
Fig. 5 is the cross-section details figure in the region of the frame (4) of container, and it illustrates two kinds of guiding piece (43 Hes
44) and MMC pipe (5) be inserted in the grid formed by stainless steel sheet material (41), guiding piece (43 and 44) form for from this
The necessary part of container removal heat system.
Fig. 6 shows the cross section according to horizontal plane of container.
Specific embodiment
As can be seen that the vessel (1) of container are mainly formed by the board group (11) of formation inner casing from the attached drawing.By circle
The bottom (12) that plate is constituted is in inner casing lower weld to inner casing.
The encapsulation piece (6) of heat-dissipation aluminum sectional material (2), neutron shielding material (3) and the neutron shield as outermost surface
It is radially disposed on inner casing.
For the ease of decontamination, in addition to four promotion axle journals (9) and pivot journal (10), the outer surface of container is by design
Be finish-machined to that it is made not have part outstanding.
The design with all related elements of the vessel (1) of container is shown in FIG. 2.Composition is described more fully below
All components of vessel.
The inner casing made of carbon steel (11) provides container and main shield member resists the structure reactance of gamma radiation.It
It can be one, can also be formed by two parts welded together.
In the upper end of shell, two seated connection surfaces (13,14) are machined, reception inner cover is bolted
(7) and outer cover (8).The sealing surface of inner cover and outer cover is protected by stainless steel cladding.Promote axle journal (9) and pivot journal (10) position
In the outside of shell.
Neutron shielding material (3) is installed in the space in heat-dissipation aluminum sectional material group (2), and the aluminum profile passes through contact
It is located on the outer surface of the shell of vessel (1).
Bottom (12) is by the circular flat board group with cylindrical heel at can be attached to cylinder by welding
On encapsulation piece.Outer surface includes multiple threaded holes, for being fixed on container traffic to CTSF or the storage of any other spentnuclear fuel
The bolt of used low impact-attenuating device when position.
Used neutron shielding material (3) is made of synthetic polymer, the synthetic polymer be when in use solid simultaneously
It and is based on the epoxy resin for being attached with boron carbide above.The material is located in the unit formed by aluminum profile.
The heat-dissipation aluminum sectional material (2) of assembling is preferably 2 to 10mm thick aluminium being radially disposed between two circular cylindrical shells and closes
Golden unit, the material wherein inserted with neutron shield part (3).Gradient between continuous sheet is 10 °, so that these radiate
Each of profile is arranged in vessel (1) or is formed about at the contact point of shell (6) relative to radius or tangent line
45 ° of angle.
Finally, shell (6) and closed-loop form cylindrical encapsulation piece, the encapsulation piece of the cylinder by with a thickness of 10 to
40 millimeters of rolling carbon steel coupon is made, and has upper and lower confining zone (referred to as ring).It by neutron shielding material (3) and this group dissipate
Hot profiles (2) limit and are isolated with the external world.Relief valve is located on the encapsulation piece, and the purpose is to limit the pressure inside encapsulation piece
Power.
Axle journal (9) are promoted to be located in the top of container.They are two firm high strength steel axle journals, and the purpose is to lift by crane
And conveying container.Each promotion axle journal passes through in a series of two positions diametrically that bolts are fixed in vessel shell
It machines in cavity.Pivot journal (10) will use in transfer or pallet for transporting during container turning operation.They are similar to
It is promoted axle journal (9).Two groups of axle journals may include cavity, neutron shielding material (2) is provided in cavity, this is because fuel element
Active length lower part in high-intensitive neutron source.Similar with axle journal is promoted, pivot journal is also fixed by bolts to vessel (1)
On.Axle journal in dual purpose Vessel Design can be " male " type or " mother " profile shaft neck, this is specifically dependent upon power plant application
Limitation or transport require.
Once load is accommodated in internal cavity, by two lids, inner cover (7) and outer cover (8) are isolated from the outside, often
A lid is able to maintain internal cavity anti-leak.Two bonnet bolts are fixed on vessel (1), there are about between two lids
5mm is to pressurize to the chamber with helium.Assuming that in the case where, if there is leakage in closed system in container, between lid
Pressure measurement in space can issue alarm.
Inner cover (7) circle plate made of low-alloy steel is constituted.A series of through-holes are with outside it, allow to pass through
Alloying carbon steel bolt attaches it to the main body of container.The lower surface for covering (7) passes through bimetallic (spring cone) seal connector (15) in vessel
(1) it is closed on seated connection surface (14), the bimetallic (spring cone) seal connector is closed system a part, and this prevent any radioactivity
A possibility that content leaks.
Outer cover (8) forms the second leakage barriers of container, i.e. redundancy barrier, and main purpose is protection closed system
Not by any kind of impact.It is made of other round plate or plate, seating face (13) of the lower surface in vessel (1)
Upper closing, and be fixed thereon with one group of alloying carbon steel bolt.The lower surface of lid is by double metal connector (15) in container
Seated connection surface on close.Once by they close blending bolts fix, will have between inner cover (7) and outer cover (8) one most
The gap of smallization, space between referred to as covering.
The outer surface of lid (8) has a series of threaded holes (81), for fixing the bolt of upper impingement attenuator.
The design of container includes three penetration pieces, encloses lid: two in inner cover (7), one in outer cover (8).
The penetration piece of venthole and drainage hole is embedded in inner cover, directly reaches the internal cavity of container, therefore be running through for closed system
Part.Pressure control penetration piece permission in outer cover detects the abnormal conditions being likely to occur in the operation of container.The draining of inner cover
Hole and venthole are respectively provided with Quick disconnection valve；After fuel loading, two penetration pieces all are used to be connected to the inner chamber body of container.
In addition, fuel frame (4) is made of three metal sub-components:
The cell structure (42) formed by one group of austenite stainless steel sheets (41), the bus relative to vessel (1) are vertical
It is connected with each other to arrangement, and by slit (411), which allows for these stainless steel sheet materials to be assembled together, and is formed and is accommodated
The unit of fuel element.All stainless steel sheet materials (41) have vertical slit, can be assembled together, to be formed rectangular
Unit.It is manufactured from the same material and there is the vertical plate (for stiffener assembly) of same thickness to be spot welded the appearance in unit grid
On face.
Fuel element occupies the inside for the pipe (5) being inserted in the unit of grid (42), and the pipe is by with neutron-absorbing
The pipe with square cross section of aluminium-boron carbide composite material (Matrix Metal Composite, MMC) manufacture of ability
Composition, this helps internal cavity being maintained at subcritical state.
Finally, the guide part (43,44) of frame is aluminium alloy extrusions, fixed fuel unit (42), and in the more of unit
The essential part of transportation system is constituted between side shape periphery and the cylindrical interior of vessel (1).Its cross section is showed with three
The unit of angular shape (44) and quadrangle form (43), and be bending always close to the face of the cylindrical encapsulation piece of vessel
's.
The guide part (43,44) of frame is screwed onto vertical stiffening plate, which is soldered to the lattice of frame (4)
On the outer surface of grid structure (42).
Fully described property and its preferred embodiment of the invention, for the intentional and purpose of institute it is hereby stated that, can
By modify described element material, in the form of, shape and arrangement, as long as this does not change the feature of invention as hereinafter claimed
Essence.
Claims (6)
1. a kind of for storing and transporting the container of spent fuel, the container of the type includes: by the vessel of cylindrical steel
(1) main body formed, the vessel (1) are closed in bottom, and are equipped with the closed system of upper latch, and the closed system is equipped with
There is leakage-preventing sealing device, the closed system provides the structure reactance of the container and the neutron shield to fuel, the device
Ware accommodates the inner frame (4) formed by stainless steel sheet material (41) grid, and the grid limits multiple units (42), Mei Gesuo
It states unit to be suitable for comprising pipe (5), the cross section of the pipe (5) is equal to the cross section of the unit, is suitable for wherein comprising big
The spent fuel of amount, which is characterized in that the frame (4) arranges around stainless steel structure (42), has rectangle and three
The guide part (43,44) of the aluminium alloy of angular cross section and curved outer surface, in the guide part and the unit
(42) cylindrical structure for adapting to the cavity of the vessel (1) is formed between grid, thus by decay heat from the frame
(4) the steel vessel (1) are transmitted to, the outer surface of the vessel has the heat sink section bar (2) of one group of aluminum, neutron shield material
Material (3) includes in space between profile and by cylindrical shell (6) from outer protection, the shell (6) will described in
Neutron shielding material (3) and this group of heat sink section bar (2) limit and are isolated with the external world, are conducive to remove heat from the container.
2. container according to claim 1, which is characterized in that the vessel (1) by formation cylindrical body at least one shell
(11) or multiple shells for welding together, and be soldered to bottom (12) composition of lower base, and in upper opening plus
There are two seated connection surface (13,14), the seated connection surfaces (13,14) to adapt to be fixed on the seat by corresponding bolt for work
Connect the inner cover (7) and outer cover (8) on surface；The bottom (12) and the outer cover (8) have a series of threaded holes (81), are transporting
Defeated period protects the impact-attenuating device of the container to be fixed in the threaded hole by corresponding bolt.
3. container according to any one of the preceding claims, which is characterized in that inner cover (7) and outer cover (8) use bolt
It is fixed in the vessel (1), and is clamped in joint by respective constraint metal joint (14,15), the constraint metal
Connector (14,15) prevents any radioactive substance leakage sealed, by the sky between the inner cover (7) and the outer cover (8)
Between or chamber pressurizeed with helium so that in the space measurement of pressure can detect it is any in the closed system in the container
Leakage.
4. container according to any one of the preceding claims, which is characterized in that be located at the vessel (1) and described outer
The heat sink section bar (2) between shell (6) is in the middle position between tangentially and radially, with the vessel (1) or described
At the contact point of shell (6), about 45 ° of angle is formed relative to radius or tangent line, and the heat sink section bar is not welded to
In the main body of the container (1), but it is fixed by the shell (6) itself.
5. container according to any one of the preceding claims, which is characterized in that solid on the outside of the vessel (1)
Surely there is pairs of axle journal (9,10) relatively diametrically, two of them promote the top that the container is arranged in axle journal (9), and
Two pivot journals (10) use during container turning operation in transfer or pallet for transporting.
6. container according to any one of the preceding claims, wherein form the region of the frame (4), receiving
The structure of the grid (42) of fuel is made of the sheet material (41) of one group of austenite stainless steel, this group of austenite stainless steel
Sheet material be longitudinally arranged relative to the bus of the vessel, which is characterized in that the sheet material (41) by vertical slit (411) that
This connection, the vertical slit allow that the sheet material is assembled together by stringent mechanical device, accommodate institute to generate
The rectangular cells of cartridge (5) are stated, the cartridge is made of aluminium-boron carbide composite material with neutron absorption capability, this
Help inner chamber body being maintained at subcritical state.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| PCT/ES2017/070130 WO2018162767A1 (en) | 2017-03-08 | 2017-03-08 | Container for storing and transporting spent nuclear fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN110506310A true CN110506310A (en) | 2019-11-26 |
Family
ID=63448210
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201780089551.1A Pending CN110506310A (en) | 2017-03-08 | 2017-03-08 | The container of storage and transport spent fuel |
Country Status (4)
| Country | Link |
|---|---|
| EP (1) | EP3594964A4 (en) |
| KR (1) | KR20190117759A (en) |
| CN (1) | CN110506310A (en) |
| WO (1) | WO2018162767A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112466500A (en) * | 2020-11-13 | 2021-03-09 | 中广核工程有限公司 | Spent fuel storage tank transport container for nuclear power station |
| CN113808770A (en) * | 2021-08-10 | 2021-12-17 | 中国核电工程有限公司 | Sealed container for storage and transportation of spent fuel assembly |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2697656C1 (en) | 2018-12-28 | 2019-08-16 | Акционерное общество "Федеральный центр ядерной и радиационной безопасности" (АО ФЦЯРБ) | Method for long-term dry storage of spent nuclear fuel and container for its implementation |
| CN110634583B (en) * | 2019-09-25 | 2022-02-22 | 中国核动力研究设计院 | Single spent fuel rod transfer container and use method thereof |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4336460A (en) * | 1979-07-25 | 1982-06-22 | Nuclear Assurance Corp. | Spent fuel cask |
| US4983352A (en) * | 1984-11-13 | 1991-01-08 | Westinghouse Electric Corp. | Closure system for a spent fuel storage cask |
| US5406600A (en) * | 1993-10-08 | 1995-04-11 | Pacific Nuclear Systems, Inc. | Transportation and storage cask for spent nuclear fuels |
| WO1998053460A2 (en) * | 1997-05-19 | 1998-11-26 | Holtec International | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
| US20020118786A1 (en) * | 2001-02-26 | 2002-08-29 | Mitsubishi Heavy Industries, Ltd. | Cask |
| JP2004069620A (en) * | 2002-08-08 | 2004-03-04 | Mitsubishi Heavy Ind Ltd | Basket for storing recycle fuel assembly and container for storing recycle fuel assembly |
| JP2007033242A (en) * | 2005-07-27 | 2007-02-08 | Hitachi Ltd | Spent fuel storage container |
| JP2008281437A (en) * | 2007-05-10 | 2008-11-20 | Toshiba Corp | Fuel storage structure of spent fuel cask |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3150669B2 (en) * | 1999-09-02 | 2001-03-26 | 三菱重工業株式会社 | Cask |
| US8548112B2 (en) * | 2006-06-30 | 2013-10-01 | Holtec International, Inc. | Spent fuel basket, apparatus and method using the same for storing high level radioactive waste |
| US20140044227A1 (en) * | 2012-08-13 | 2014-02-13 | Transnuclear, Inc. | Composite basket assembly |
-
2017
- 2017-03-08 EP EP17899513.0A patent/EP3594964A4/en not_active Withdrawn
- 2017-03-08 CN CN201780089551.1A patent/CN110506310A/en active Pending
- 2017-03-08 WO PCT/ES2017/070130 patent/WO2018162767A1/en unknown
- 2017-03-08 KR KR1020197028407A patent/KR20190117759A/en not_active Application Discontinuation
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4336460A (en) * | 1979-07-25 | 1982-06-22 | Nuclear Assurance Corp. | Spent fuel cask |
| US4983352A (en) * | 1984-11-13 | 1991-01-08 | Westinghouse Electric Corp. | Closure system for a spent fuel storage cask |
| US5406600A (en) * | 1993-10-08 | 1995-04-11 | Pacific Nuclear Systems, Inc. | Transportation and storage cask for spent nuclear fuels |
| WO1998053460A2 (en) * | 1997-05-19 | 1998-11-26 | Holtec International | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
| US20020118786A1 (en) * | 2001-02-26 | 2002-08-29 | Mitsubishi Heavy Industries, Ltd. | Cask |
| JP2004069620A (en) * | 2002-08-08 | 2004-03-04 | Mitsubishi Heavy Ind Ltd | Basket for storing recycle fuel assembly and container for storing recycle fuel assembly |
| JP2007033242A (en) * | 2005-07-27 | 2007-02-08 | Hitachi Ltd | Spent fuel storage container |
| JP2008281437A (en) * | 2007-05-10 | 2008-11-20 | Toshiba Corp | Fuel storage structure of spent fuel cask |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112466500A (en) * | 2020-11-13 | 2021-03-09 | 中广核工程有限公司 | Spent fuel storage tank transport container for nuclear power station |
| WO2022033606A1 (en) * | 2020-11-13 | 2022-02-17 | 中广核工程有限公司 | Transportation container for nuclear power station spent fuel storage tank |
| CN113808770A (en) * | 2021-08-10 | 2021-12-17 | 中国核电工程有限公司 | Sealed container for storage and transportation of spent fuel assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| WO2018162767A1 (en) | 2018-09-13 |
| EP3594964A4 (en) | 2020-11-11 |
| KR20190117759A (en) | 2019-10-16 |
| EP3594964A1 (en) | 2020-01-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110506310A (en) | The container of storage and transport spent fuel | |
| RU2348085C1 (en) | Container for transportation and/or storage of waste nuclear fuel | |
| US20100272225A1 (en) | Cask apparatus, system and method for transporting and/or storing high level waste | |
| US9466400B2 (en) | Ventilated transfer cask with lifting feature | |
| US9786393B2 (en) | Passive reactor containment protection system | |
| US3828197A (en) | Radioactive waste storage | |
| US11676736B2 (en) | Ventilated metal storage overpack (VMSO) | |
| US11430579B2 (en) | Apparatus and methods for storing hazardous waste materials by encasing same in a fusible metal alloy | |
| JP2006275730A (en) | Structure of cask | |
| RU2084975C1 (en) | Container for spent fuel transporting and/or storage | |
| CN110867267A (en) | Spent fuel storage and transportation container | |
| US8822964B2 (en) | Radioactive substance storage container | |
| US4687625A (en) | Piping of nuclear reactor containment vessel | |
| KR100270805B1 (en) | Radioactive isotope transportation cask for hydraulic transfer system | |
| RU2458417C1 (en) | Cover for spent fuel assemblies | |
| Janberg et al. | Status of the development of final disposal casks and prospects in Germany | |
| US20030198313A1 (en) | Thermal shunts and method for dry storage of spent nuclear fuel | |
| RU2141138C1 (en) | Shielding container storage arrangement and shielding container for transportation and storage of pressurized-vessel reactor | |
| Jobson et al. | Castor® X/32 s—a New Dual-Purpose Cask for the Storage and Transport of Spent Nuclear Fuel | |
| Hanson et al. | International experience of storing spent fuel in NUHOMS® systems | |
| Shih et al. | NUHOMS {sup registered}-MP197 transport cask | |
| Chung et al. | Conceptual design for KN-12 spent fuel shipping cask | |
| Chung et al. | Evaluation of the KN-12 spent fuel transport cask by analysis | |
| Hunter et al. | Adapting the NUHOMS Interim Storage System for international spent fuel storage needs | |
| Leers et al. | The safety of transport operations and transport casks for LWR and VVER spent fuel |
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 | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20191126 |
|
| WD01 | Invention patent application deemed withdrawn after publication |