This invention relates to a device for storing nuclear fuel and a vessel for inclusion in such device.
When spent nuclear fuel is taken out of a reactor in a nuclear power plant, it is commonly placed in a pool in the vicinity of the reactor, in most cases within the nuclear power plant, pending transport to a reprocessing site or to a repository for long-term storage, such as a site for final disposal. During one or more stages of its management, the nuclear fuel is stored in a container of one kind or another. This container may be of different kinds, depending on whether the storage is temporary, such as when the container is used to accommodate the nuclear fuel only while waiting for shipping or during transport from one place to another, or of a long-term character.
In this context it is known to use an inner container formed by a closed vessel which accommodates the hazardous material, that is, the nuclear fuel and which is itself contained in an outer container formed by a concrete body, see WO96/21932. The vessel forming the inner container is completely encapsulated in the concrete, the concrete providing the major part of the mechanical protection for the hazardous material and of the protection against radiation from it.
Associated with devices used for the storage of spent nuclear fuel, that is, nuclear fuel that continues to generate heat when removed from the reactor, is the problem of avoiding excessive temperatures of the device. If the vessel forming the inner container is encapsulated in the concrete, an excessive temperature may affect the concrete in course of time.
The heat generated in the inner container therefore has to be efficiently dissipated from the container and at the same time the temperature throughout the concrete body has to be kept sufficiently low so that the ageing resistance of the concrete and its ability to provide radiation protection are not seriously reduced over the time the nuclear fuel is to be stored.
An object of the invention is to provide a device of the kind indicated which offers the possibility of lastingly maintaining the concrete body at a low temperature even in the parts thereof which are closest to the vessel forming the inner container, and also a vessel suited for use as an inner container for such a device.
A device according to the invention for storing heat-generating hazardous material, particularly radioactive fuel for nuclear reactors, comprises a substantially cylindrical, reinforced concrete body with a cylindrical through centre passage and a plurality of axially elongate, substantially cylindrical storage spaces for accommodating the hazardous material which are disposed around and parallel to and radially spaced from the centre passage. The storage spaces are formed by sealed storage vessels containing a fluid coolant and made of a heat-conducting material and encapsulated in the concrete body. The storage vessels have an inner compartment for accommodating the hazardous material and an outer compartment surrounding the inner compartment and forming therewith a closed circulation path for the fluid coolant.
An inner container according to the invention, hereinafter designated the storage vessel, comprises a cylindrical outer wall and a surrounding, likewise cylindrical outer wall. The inner wall defines an inner compartment for accommodating the material to be stored (the nuclear fuel). The inner wall and the outer wall delimit an intervening outer compartment surrounding the inner compartment. The two compartments are interconnected and form a closed flow path for a fluid coolant which can circulate axially through the two compartments. When the storage vessel is encapsulated in a concrete body, the fluid coolant cools the stored material and is in its turn cooled by the outer wall which is in direct contact with the concrete body. By means of the surface of the outer wall in contact with the concrete body and the use of the circulating fluid coolant the heat is distributed over a relatively larger surface so that the thermal load on the concrete will be reduced.
The invention will be described in greater detail below with reference to the accompanying drawings which show examples of the device and the storage vessel.
Referring to
The centre passage 13, which is extended through the lower end cover 15a and the upper end cover 15A, is provided with a steel lining 20 which is also a permanent casting formwork member. As is best shown in
Four hermetically sealed, circular cylindrical inner containers form storage vessels for the stored hazardous material, which in this case is nuclear fuel. These storage vessels are generally designated by 21 and encapsulated in the concrete body 11 at some distance from the lining 20 but much closer to the latter than to the jacket 14. The storage vessels 21, which will be described in greater detail below, are uniformly distributed in the concrete body around the lining 20 and are equally spaced apart from the latter and from one another. They are placed in an upright position, axially aligned with concrete-filled openings 15a and 15b in the end covers 15A, 15B; these openings have been filled with concrete in connection with the casting of the concrete body 11. Should it become necessary to get access to the stored nuclear fuel in the storage vessels 21, the concrete above or below the storage vessels can be removed, e.g. by means of drilling tools, so that one end of the storage vessels becomes exposed. Then the exposed end can be opened using suitable tools so that the nuclear fuel can be extracted.
The nuclear fuel can be placed in the storage vessels 21 after these have been positioned in the formwork or, alternatively, before positioning the vessels therein (for practical reasons, this alternative is a necessity with the embodiment shown in
Those parts of the storage vessel 21 which are in contact with the concrete of the concrete body, that is, the outer wall 22, the bottom wall 23, and the parts at the sealing end of the storage vessel, namely the ring 26 and the cover 28, suitably are made of metal, preferably stainless steel, or other material having good corrosion resistance, strength and heat conductivity.
The storage vessel 21 contains a fluid coolant which can flow freely between the outer compartment 25 and the inner compartment 27 through the openings 24a in the inner wall 24. In
The nuclear fuel stored in the storage vessel 21 may take different forms and can be, for example, a fuel element or a bundle of fuel rods. In
The lower holder body 29 rests on the bottom wall 23. The upper holder body 30 is supported against the cover 28 through a hollow filler body 31, the cavity of which communicates with the outer compartment 25 and the inner compartment 27. The free spaces in the compartments 25 and 27 and the filler body 31 form an expansion chamber. The holder bodies 29, 30 are shaped such that they surround the respective adjacent ends of the fuel body B so that they support and locate it laterally and at the same time support and locate it axially.
Both holder bodies 29, 30 have a wide, centrally located, axially extending through passage and a large number of smaller, axial and transverse passages. The system of passages in the holder bodies is structured such that the fluid coolant can flow almost without impediment along the outer surfaces of the fuel body B even where the support bodies are located.
When the fuel body B is in position in the storage vessel 21, the fluid coolant will circulate in the storage vessel by natural convection caused by the heat produced in the fuel body B, the fluid coolant flowing upwardly in the inner compartment 27 along the sides of the fuel body and, where the structure of the fuel body permits, also within the fuel body, and is then deflected 180° at the upper end of the storage vessel 21 and flows downwardly in the outer compartment 25. At the upper holder body 30 the fluid coolant flows substantially unimpeded through the central axial passage of the holder body and its transverse passages and then from the inner compartment 27 to the outer compartment 25 via the openings 24a in the upper part of the inner wall 24. At the lower holder body 29, the fluid coolant flows in a corresponding manner from the outer compartment 25 into the inner compartment 27 via the openings 24a in the lower part of the inner wall 24 and through the transverse passages and the central axial passage of the holder body. Because of the heat insulating properties of the holder bodies 29, 30 the holder bodies do not form any undesired heat-conducting bridge that transfers heat direct to the inner wall 24.
Because of its circulation, the fluid coolant transfers heat to the outer compartment 25 where the heat is transferred to the concrete body as a consequence of the contact with the outer wall 22. The major part of the heat passes through the lining 20 into the air in the centre passage 13 of the concrete body 11 and via the air away from the storage device 10. The remaining, smaller part passes outwardly to the jacket 14 of the storage device and via the jacket to the ambient air.
Between each storage vessel 21 and the steel sheet lining 20 covering the wall of the centre passage 13 in the concrete body 11 a metal bar 32 is positioned which is connected in heat-transfer relation to the outer wall 22 of the storage vessel and the lining 20. This bar 32, which extends throughout or nearly throughout the height of the storage device 10 or at least nearly throughout the height of the storage vessel 21, forms a member having high heat conductivity for transferring heat from the storage vessel and the concrete adjacent to the storage vessel to the air in the centre passage 13. Although the figure shows only one such heat-transfer member, it will be appreciated that additional similar members may be provided to improve the heat transfer.
In the interest of clarity of the illustration of the invention, the representation of the storage device 10 and the storage vessels 21 in FIGS. 1 to 4 is greatly simplified. It is quite easy for the skilled person to accomplish the structural design of the storage device and the storage vessel which is required to reduce the invention to practice, taking into consideration the kind of nuclear fuel or other hazardous material to be stored and the purpose of the storage.
The storage vessel in
In this embodiment, the outer compartment 25 communicates with the inner compartment 27 across the upper and lower edges of the inner wall 24 which for that reason does not have openings corresponding to the openings 24a in FIGS. 2 to 4. To keep the inner wall 24 in position relative to the outer wall 22, transverse supports 22A and a support body 33, of generally cruciform shape in plan view and made of concrete, for example, are provided at the bottom end of the storage vessel. The support body 33 has a round base, the bottom side of which is of a shape corresponding to the shape of the inner side of the lower end of the storage vessel, that is, the shape of the bottom wall 23, and is weighted such that it contributes to keeping the storage vessel upright when it is immersed in water.
In this embodiment as well, the holder bodies 29, 30 are made of a heat-insulating material of long-term stability even at elevated temperatures, such as foam glass, but are of cruciform shape with upstanding support lugs at the free ends of the arms. The upper holder body 29 is supported from above by another cruciform support body 34 having a tubular shank secured to the dome-shaped cover 28. The lower holder body 30 rests on the support body 33.
The fluid coolant in this case is a gas, such as nitrogen, but circulates in substantially the same manner in a closed circulation circuit formed by the outer compartment 25, the inner compartment 27, the bottom wall 23 and the cover 28. The cruciform shape of the holder bodies 29, 30 and the support bodies 33 and 34 provides ample space for the flow of the fluid coolant between the compartments 25 and 27.
In the cover 28 and the support bodies 33, 34 valves 35 are provided through which the storage vessel can be filled with the fluid coolant.
In this embodiment the storage vessel 21 is sealed by welding the cover 28 to the outer wall 22. Introduction of the fuel body B and welding of the cover suitably are carried out on a site separated from the site where the concrete body 11 is cast. Following its sealing, the loaded storage vessel 21 is transferred to the casting site where it is placed in the permanent casting formwork comprising the jacket 14, the end covers 15A, 15B and the lining 20 (see
In the embodiment of
Regardless of the design of the storage vessel 21, its innermost part, the part closest to the lining, should be sufficiently spaced from the lining to ensure both a problem-free pouring of the concrete around the storage vessel and an adequate mechanical protection of the storage vessel. Having regard to these requirements, the spacing may be 10 to 15 cm or possibly, especially if the lining 20 is thick, slightly less. Such small spacing may not be adequate to make the radiation in the passage 13 without risk or harmless to humans, but since humans are not supposed to be in that passage, this is not a major problem. Having regard to the cooling, the spacing should be as small as possible in order that the heat transfer from the storage vessel 21 to the passage 13 may be as efficient as possible, but in view of the above-mentioned requirements with respect to problem-free encapsulation and mechanical protection, a lower limit must be observed. The minimum spacing should therefore preferably be from about 10 cm to about 15 cm.
The requirement for efficient dissipation of heat from the passage also calls for a certain minimum diameter of the passage. If the storage device 10 is kept in air and loaded with four storage vessels 21, each having a heat generation of 1200 W, for example, a diameter of 600 to 700 mm or slightly more is suitable with natural convection in the passage 13. Adequate cooling can be had even with a diameter less than 600 mm if the air flow in the passage 13 is forced or if the storage device 10 is submerged in water.
The concrete between the outermost part of the storage vessels 21 and the jacket 14 should be adequate for the temperature at the outer surface of the storage device 10 not to exceed a limit of, for example 100° C. If that limit applies, 60 cm may be a preferred minimum distance between the outermost part of the storage vessels 21 and the jacket 14 if the concrete body consists of ordinary concrete. If a higher degree of safety is required or desired, 70 cm may be a preferred minimum distance. Some reduction of the stated minimum values may be possible, e.g. if so-called iron-ore concrete is used.
Number | Date | Country | Kind |
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0100247-6 | Jan 2001 | SE | national |
This application is a divisional of application Ser. No. 10/470,341, which is the National Stage of International Application No. PCT/SE02/00151, filed Jan. 29, 2002.
Number | Date | Country | |
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Parent | 10470341 | Jul 2003 | US |
Child | 11062817 | Feb 2005 | US |