The present teachings relate to nuclear reactor fuel bundles and more particularly to the spacer grids that group the fuel rods of the bundles within the channels of the fuel bundles.
The statements in this section merely provide background information related to the present disclosure and may not constitute prior art.
Nuclear reactors, such as boiling water reactors, generally include a reactor core comprised of many fuel bundles through which, and around which, a liquid moderator, e.g., liquid water, flows. Nuclear reactions within the fuel bundles generate heat used to convert the moderator to steam as the moderator passes through the core. The steam is then used to generate electrical power. Each of the fuel bundles typically includes a plurality of sealed and vertically upstanding fuel rods housed within an elongate tubular channel. Within the channel, the fuel rods of each fuel bundle are held in a spaced apart configuration by two or more spacer grids comprised of a plurality of interconnected spacers that form a plurality of rows and columns of open cells. Each cell has a respective one of the otherwise long and flexible fuel rods extending therethrough and serves to prevent the fuel rods from coming into abrading contact one with another under the dynamics of moderator flow within the reactor. The spacers additionally maintain the designed fuel rod to fuel rod spacing for optimum nuclear performance. The spacer grids typically include a perimeter band that provides an outer defining envelope for the spacer cells and the fuel rods placed therein.
Known spacer grid designs are typically sized such that a small gap exists between the perimeter band and the walls of the channel that allows the grouped fuel rods, i.e., the fuel rods retained within the spacer grids, to be more easily inserted into the respective channels. However, this gap allows movement of the grouped fuel rods within the respective channels. For example, when the fuel bundles are placed within a reactor, such movement can be caused by many forces within the reactor, such as the moderator flow. Movement of the grouped fuel rods within a reactor can cause some of the peripheral, i.e., outermost, fuel rods of the group to move towards the channel walls while other peripheral fuel rods are moved away from the channel walls. When any of the peripheral fuel rods move toward one or more of the channel walls, the flow of the moderating coolant is inhibited at these highly reactive fuel rods. Inhibition of coolant flow causes critical power losses at these peripheral fuel rods, especially at the fuel rods adjacent the corners of the channel. As a result, the entire fuel bundle must be limited in its performance so that these critical power limits of the peripheral fuel rods are not exceeded.
Another example of the grouped fuel rods moving within the respective channel occurs during shipping of the fuel bundles. During shipping, the gap between the channel and the spacer grids can allow the grouped fuel rods to move, or ‘rattle’, within the channels and cause structural damage to the spacers grids and fretting damage to the fuel rods.
A further disadvantage of known spacer grids, particularly the perimeter band, is that the structural design of such spacer grids can inhibit the flow of coolant between the channel walls and the peripheral fuel rods, which can limit the energy generating potential of the peripheral fuel rods. Further yet, the perimeter bands do little or nothing to ‘strip’ coolant from the channel walls so that the coolant is utilized to cool the grouped fuel rods.
According to one aspect, a spacer grid for a nuclear reactor fuel bundle is provided. In various embodiments the spacer grid includes a plurality of interstitial dividers that form an array of cells. Each cell is structured to retain a respective one of a plurality of fuel rods to form an array of equally spaced fuel rods. The spacer grid additionally includes a perimeter band peripherally surrounding the dividers and connected to opposing ends of each divider. The perimeter band includes a plurality of spring tabs formed along an edge of the perimeter band. The spring tabs extend from the edge at an angle away from the dividers such that a distal end of each spring tab will contact an interior surface of a respective one of a plurality of walls of a channel in which the arrayed fuel rods can be inserted to form the fuel bundle.
According to another aspect, a fuel bundle for a nuclear reactor is provided. In various embodiments, the fuel bundle includes a plurality of fuel rods, a spacer grid including a plurality of interstitial dividers, and a perimeter band peripherally surrounding the dividers. The perimeter band is connected to opposing ends of each divider to form an array of cells. Each cell structured to have a respective one of the fuel rods received therein to form an array of equally spaced fuel rods. The fuel bundle additionally includes an elongate tubular channel in which the arrayed fuel rods are housed. A plurality of spring tabs extend from an edge of the perimeter band at an angle away from the dividers such that a distal end of each spring tab contacts an interior surface of a respective one of a plurality of walls of the channel.
Further areas of applicability of the present teachings will become apparent from the description provided herein. It should be understood that the description and specific examples are intended for purposes of illustration only and are not intended to limit the scope of the present teachings.
The drawings described herein are for illustration purposes only and are not intended to limit the scope of the present teachings in any way.
The following description is merely exemplary in nature and is in no way intended to limit the present teachings, application, or uses. Throughout this specification, like reference numerals will be used to refer to like elements.
Referring to
The fuel bundle 14A generally includes a plurality of fuel rods 18 positioned within an elongate tubular channel 22 and held in a spaced apart relation with each other by at least one spacer grid 26. As described below, the spacer grid 26 is designed to: 1) maintain the arrayed fuel rods 18 substantially centered within the channel 22 to increase the power potential for the fuel bundle 14A; 2) greatly reduce structural damage to the spacer grids 26 and fretting damage to the fuel rods 18 that may occur during shipping of the fuel bundle 14A; and 3) assist in stripping entrained liquid moderator from the interior surfaces of the channel 22 as the liquid moderator flows through the channel 22 and around the fuel rods 18.
Although
Referring now to
As illustrated, the perimeter band 38 forms the outer sides of the peripheral cells 34, i.e., the outermost cells along the periphery of the cell array. Thus, the perimeter band 38 forms four sides of spacer grid 26. As best illustrated in
The angle θ can be any angle suitable to provide simultaneous contact of each of the spring tabs 46 with each of the respective interior surfaces 58 of the respective channel walls 62. More particularly, the perimeter band 38 and spring tabs 46 are structured to have an angle θ such that each spring tab 46 independently and simultaneously exerts a desired spring force against the respective interior surface 58. Thus, each spring tab 46 is formed as separate and independent structure from the other spring tabs 46 and applies a separate, independent spring force against the channel walls 62 that is based on the angle θ. In various embodiments, the angle θ of each spring tab 46 is substantially identical such that each spring tab 46 applies substantially equal force to the channel walls 62. In various alternate embodiments, various different spring tabs 46 extend from the edge 50 at various different angles θ, such that different spring tabs 46 apply different spring forces against the channel walls 62.
The spring tabs 46 apply force against the channel walls 62 such that the spacer grid 26, and thus the arrayed fuel rods 18, is retained in a laterally centered orientation within the channel 22 when the channel 22 is installed in the reactor. By maintaining the arrayed fuel rods 18 in a laterally centered orientation, i.e., substantially centered about a longitudinal center axis of the channel 22, power generation of the fuel bundle 14A can be maximized. As illustrated in
In various other embodiments, in order to minimize the pressure drop impact of the curved back spring tab distal end 54, the distal end 54 of one or more of the spring tabs 46 can include a radius 56 (indicated in phantom in
Furthermore, in various embodiments, the perimeter band 38 and spring tabs 46 are structured such that the spring tabs 46 apply sufficient spring force against the channel wall interior surfaces 58 to substantially reduce the risk of damage to the arrayed fuel rods 18 within the channel 22 during shipping of the fuel bundle 14A More particularly, the perimeter band 38 and spring tabs 46 are structured such that the spring tabs 46 apply sufficient spring force against the channel wall interior surfaces 58 to dampen lateral movement of the arrayed fuel rods 18 within the channel during shipping, thereby preventing damage to the fuel rods during shipping of the fuel bundle 14A.
Further yet, in various embodiments, the perimeter band 38 and spring tabs 46 are structured such that the spring tabs 46 apply sufficient spring force against the channel wall interior surfaces 58 to strip liquid moderator entrained on the channel wall interior surfaces 58 from the respective surfaces 58. That is, when fuel bundle 14A, as described above, is installed in the core of a nuclear reactor and a coolant is passed through the core and fuel bundle 14A, the spring tabs 46 will interfere with the flow of coolant that is entrained on the channel wall interior surfaces 58 to break up the entrained coolant flow and direct it toward the fuel rods 18. Thus, the spring tabs 46 are structured to contact the interior surfaces 58 with sufficient force to strip the entrained liquid moderator and direct the stripped liquid moderator toward the fuel rods 18, thereby increasing the thermo-nuclear power generating efficiency of the fuel bundle 14A.
As described above, the perimeter band 38 forms the outer sides of the cell array, i.e., the four sides of the spacer grid 26. In various embodiments, spacer grid 26 includes the four sides and at least one beveled corner 66. Additionally, in various embodiments, a corner spring tab 46A extends away from the edge 50 of each beveled corner 66 at the angle θ such that a distal end 54A of each corner spring tab 46A will contact the interior surface 58 of a respective corner of the channel 22.
Referring now to
Referring again to
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Ultimately, the positioning and spacing of the spring tabs 46 along the sides and beveled corners of the spacer grid 26 can be selectively chosen to provide optimal critical power and pressure drop performance of the fuel bundle 14A within the nuclear reactor.
Accordingly, as described herein, the spacer grid 26 of the fuel bundle 14A is structured to maintain the arrayed fuel rods 18 laterally centered within the channel 22, greatly reducing structural damage to the spacer grids 26 and fretting damage to the fuel rods 18 that may occur during shipping of the fuel bundle 14A, and assist in stripping entrained liquid moderator from the interior surfaces 58 of the channel 22. Therefore, the spacer grid 26 increases the power potential for the fuel bundle 14A when it is utilized in a reactor and protects the fuel rods 18 from damage during shipping.
The description herein is merely exemplary in nature and, thus, variations that do not depart from the gist of that which is described are intended to be within the scope of the teachings. Such variations are not to be regarded as a departure from the spirit and scope of the teachings.
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Number | Date | Country |
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64-006793 | Jan 1989 | JP |
01006793 | Jan 1989 | JP |
03-030894 | Feb 1991 | JP |
Entry |
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English Translation of Japanese Patent Application Publication No. 01006793 (“Narabayashi”). |
Japan Notice of Allowance dated Mar. 19, 2013 and English Translation thereof. |
Number | Date | Country | |
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20080267340 A1 | Oct 2008 | US |