Patent Application
20090034676
The present invention relates to a nuclear fuel rod assembly for a boiling water reactor (BWR) and, particularly, relates to a water rod in the assembly.
A fuel assembly in a boiling water nuclear reactor typically includes a matrix of parallel fuel and water rods held in place by spacers and upper and lower tie plates. The fuel rods contain fissionable fuel in an enriched fuel section of the rods. Many of the fuel rods generally extend the entire vertical distance between the upper and lower tie plates, and some of the fuel rods may extend part-way up the assembly from the lower tie plate. The water rods provide additional liquid water moderator flow through the interior of the fuel assembly. Spacers are arranged at various locations along the vertical length of the fuel assembly and hold the fuel rods and water rods in a fixed relationship in the fuel assembly. The lower ends of the fuel rods and water rods have end plugs that fit into the lower tie plate which supports the rods. The lower tie plate includes flow holes to provide an inlet for moderator and coolant flow to the fuel assembly and moderator. The upper tie plate receives the upper ends of the rods, restrains lateral movement of the fuel rods and water rods, and has flow holes to discharge coolant from the fuel assembly.
A nuclear reactor fuel bundle assembly has been developed that includes: a fuel bundle including an array of fuel rods attached to a lower tie plate, an upper tie plate and a channel, and a water rod or rods having an upper discharge end below and unattached to the upper tie plate.
In another embodiment, the nuclear reactor fuel bundle assembly comprises: a fuel bundle including an array of fuel rods mounted in an upper tie plate and housed by a channel wall, and a first water rod having an upper discharge end below and unattached to the upper tie plate, and a second water rod having an upper discharge end at an elevation in the assembly that is different than the elevation of the discharge end of the first water rod.
A method has been developed to include a water rod in a nuclear reactor fuel bundle assembly including an array of fuel rods attached to an upper tie plate and housed in a channel, the method comprising: selecting a plurality of water rods; inserting the water rods in the assembly, and arranging an upper discharge end of one of the water rods to be at an elevation in the assembly different from an elevation of an upper discharge end of another one of the water rods.
The illustration of the channel and portions of several of the fuel rods in
The fuel bundle assembly 10 is arranged vertically in a boiling water reactor (BWR) 1. Several hundred fuel assemblies are typically arranged in a matrix in the water filled core of a BWR. In each fuel bundle assembly, moderator and coolant, e.g., water, flows upwards through the core and fuel bundle assemblies and is circulated back to the bottom of the core.
Coolant and moderator liquid, e.g., water, flows up through each individual fuel bundle assembly in the BWR core. The coolant and moderator liquid enters the bottom of the assembly and flows through the lower tie plate 16. An open mesh structure of the lower tie plate allows liquid to flow through the interior of the channel 20 and along the fuel rods in the assembly. The water rods 19 increase the amount of liquid water moderator in the fuel bundle assembly.
As the coolant and moderator liquid flows through each fuel bundle assembly, the liquid extracts heat from the fuel rods and provides a safeguard to prevent excessive heating of the fuel rods. The liquid may be converted to steam, especially in the upper elevations of the fuel bundle assemblies. As the heated fluid, e.g., steam, flows from the core, heat is extracted and used for power production and the cooled fluid is returned to the bottom of the core for reuse as coolant and moderator. The motive force for circulation of the coolant and moderator fluid through the BWR core may be natural circulation, or due to pumping of the coolant water through the core.
The coolant and moderator liquid flowing up through the fuel bundle assembly also serves as a moderator to the nuclear reaction occurring within the enriched portions of the fuel rods. The moderator function of the liquid is in addition to the coolant function of the liquid. The moderator function of the liquid is sharply lessened as the liquid is converted to steam. The fluid flowing along the fuel rods and up through a fuel bundle assembly has typically been mostly converted to steam as the fluid reaches the upper elevations of the fuel rods, such as the upper one third to one quarter of the fuel rods.
Water rods 19 provide a passage for liquid moderator to flow to the upper elevations of the fuel assembly. The liquid in the water rods tends to have a velocity greater than the average fluid velocity moving up between the fuel rods. The liquid in the water rod is also separated from the hot surfaces of the fuel rods. The liquid in the water rods remains as a liquid at the upper elevations of the fuel bundle assembly where much of the fluid flowing between the fuel rods has been converted to steam. The liquid in the water rods serves as a moderator to the upper elevations of the fuel rods, particularly along the upper sections of the rod that are surrounded by steam. Accordingly, there is a moderation function benefit to liquid flowing through the water rods up to an elevation at least as high as the top end of the enriched section of the fuel rods.
The steam fluid in the upper elevations of the fuel bundle require a substantially greater passage volume than does the primarily liquid flowing through lower elevations of the fuel bundle. Due to the higher volume of the steam, there is a need to increase the passage area within the upper elevations of the fuel bundle. Without a substantial increase in passage area in the upper elevations of the fuel bundle, the steam will be constricted by the channel and rods, and will cause a pressure increase that inhibits the passage of coolant and moderator through the entire fuel bundle assembly. Increasing the coolant passage area in the upper elevations of the fuel bundle should reduce the steam pressure in the upper elevations and thus reduce the pressure difference between the lower and upper elevations of the fuel bundle.
The coolant passage in the upper elevations of the fuel bundle can be increased by terminating one or more of the water rods at an elevation(s) below the upper tie plate. Ending a water rod expands the area available to the coolant, e.g., steam, to flow up above the end of the water rod and continue through the fuel bundle. The area for steam passage increases by the cross-sectional area of the water rod(s) that are terminated. In addition, the liquid discharged from the water rod may continue to serve as a moderator, especially as the liquid rises in the fuel bundle assembly and before it is converted to steam. Further, the liquid discharged from the upper end of a water rod can serve as coolant, especially if the liquid flows to the surfaces of the fuel rods.
The pressure drop through the fuel bundle is reduced due to the additional coolant passage area obtained by the termination of the upper end(s) of the water rod(s) below the upper tie plate. Reducing the pressure drop allows for greater volume of coolant and moderator fluids to pass up through the fuel bundle.
A balance is to be achieved between ensuring that sufficient moderation liquid reaches the upper elevations of the enriched portions of the fuel rods and that the pressure drop through the fuel bundle is minimized. On the other hand, terminating the upper ends of the water rods may reduce the volume of moderator liquid that reaches the upper elevations of the bundle. On the other hand, an excessive pressure drop in the fluid passages in the fuel bundle assembly may restrict the volume of coolant and moderator fluid passing through the bundle assembly. The pressure drop can be reduced by increasing the available coolant passage area between the fuel rods, especially in the upper elevations of the fuel bundle assembly where much of the coolant has converted to steam. Terminating the water rods at elevations were the fuel rods are enriched reduces the volume of moderator liquid at the upper sections of the fuel rods, but increases the coolant passage area reduces the pressure drop through the assembly and thereby increases the rate of fluid passing through the assembly. The need for a balance between coolant passage area and moderator flow is greatest with natural circulation reactors which need low pressure losses in coolant flow through the fuel bundle assemblies to promote circulation through the assemblies of the coolant and moderator fluid.
A designer of the fuel bundle assembly can balance the need for moderator liquid in the upper elevations of the enriched portion of the fuel rods with the need for greater fluid passage area in the upper elevations at and above the enriched portions of the fuel bundle. The balancing process can utilize commonly used fuel bundle molding programs and/or trial and error. Available approaches to achieving a balance include: multiple water rods which each have an upper end that discharges liquid at different elevations in the fuel bundle, and at least one water rod terminating above the enriched portion of the fuel rods. Preferably, at least one water rod discharges liquid above the enriched portion of the fuel bundle assembly, to ensure that moderator liquid passes through all elevations of the enriched portion of the fuel bundle assembly.
The lower end section 24 of the water rod may be attached to the lower tie plate 16 and include coolant inlet ports. The bottom of the lower end section 24 may be threaded to engage a treaded aperture in the lower tie plate or use other engagement methods. Further, the lower tie plate may include coolant flow path(s) for coolant flow up into the water rod(s). The lower end section 24 may comprises a narrow diameter cylindrical section that includes a plurality of side coolant inlet ports. A transition section 28 in the water rod expands the internal diameter of the rod from the lower end section 24 to the upper section 30.
By way of example, the lower section 24 may be a relatively short portion of the water rod, e.g., two to five feet (0.6 to 1.5 meters); the transition section 28 may be two to less than one foot (0.6 to less than 0.3 meters) in length, and the upper section 30 may extend 10 to 13 feet (3 to 4 meters) in length. The cross-sectional shape of the water rod may be circular, curvilinear, rectangular, cruciform shape, or a combination of curved and straight segments. A cross-sectional area of the water rod may be, for example, 1.55 square inches (10 square centimeters) at the upper section 30. Preferably the cross-sectional shape of the water rod is uniform along the length of at least the upper section 30 to promote laminar flow through the water rod and reduce flow resistance. The water rod is supported in the assembly at least by the spacers 18 and may be supported by the lower tie plate 16. The water rod may be a metallic material suitable for use in a nuclear reactor core such as zirconium based alloys.
The upper end 34 water rod terminates below the upper tie plate 14 and does not extend to the upper tie plate. Moderator, e.g., water, is discharged from the end 34 of the water rod and mixes with the coolant, e.g., water and/or steam, flowing in through the channel 20 and between the fuel rods 12. The upper end 34 of the water rod may be either above or below the enriched portion of the fuel rods. At least one water rod may terminate at an elevation in the fuel bundle assembly where a substantial portion, e.g., 25% to 75% of the coolant has converted to steam.
Preferably, the upper discharge end of the water rod is a simple open-end structure 34, such as a circular end of a cylindrical water rod. The diameter at the discharge end should be at least as large as a maximum diameter of the water rod. The simple open-ended discharge structure reduces the discharge resistance to the flow in the water rod. The open-end 34 of the water rod may be a straight walled end, curved slightly outward as a cone or horn, have other such wide mouth shapes, or be curved inward creating a slight restriction. Moderator from the water rod flows through the open-ended discharge structure 34 and mixes with the coolant flow through the channel 20 and between the fuel rods 12.
The open-ended discharge structure 34 of the upper outlet of the water rod 19 is preferably substantially free of flow restrictions. For example, the open-ended structure 34 does not have flow restriction plates, meshes or nozzles that would restrict flow through the rod and increase the pressure drop of the coolant flowing through the rod. Further, the walls of the water rod 19 do not curve inward at the open-ended structure 34 to form a nozzle or otherwise restrict the flow through the rod.
The water rods 42, 44 have open ends 46 at any different elevation within the fuel bundle assembly 40. The difference in the elevations may be, for example, six inches, one foot or three feet (15 centimeters, 30 centimeters or 0.9 meter), between the open ends 46 of the water rods 42, 44. The different elevations, e.g., 3 inches, 6 inches or a foot (9 cm; 18 cm or 36 cm) of the open ends 46 of the water rod results in moderator from each water rod being discharged at different elevations within the channel 20. The ends 46 of the water rods 42, 44 may be arranged to discharge moderator at different elevations in the channel to provide additional coolant to the fuel rods at selected elevations. As the liquid fluid flows up the water rod, the liquid primarily servers as a moderator for the fuel bundle assembly. As it is discharged from the top of the water rod, the liquid also serves as a coolant to the extent that it is applied to the fuel rods and is converted to steam. In addition, the standard length cooling rods may be included in the assembly 40. Water rods of different standard lengths may be purposefully included in an assembly to provide moderator discharge at different elevations in the channel. Discharging moderator at different elevations from multiple water rods may enhance the flow of coolant to various elevations of the fuel rods as compared to discharging multiple water rods at the same elevation in the assembly 40.
The lower sections 46, 48 of the water rod may optionally not extend to the lower tie plate 16. For example, the lower section 46 of water rod 42 may be a straight sided cylinder having a uniform diameter with the rest of the water rod 42. The straight sided cylinder lower section 46 of the water rod may terminate one or more feet, e.g., one to four feet (0.3 to 1.2 meters) above the lower tie plate. Coolant flowing up through the channel and between the fuel rods 12 enters the lower section of the water rod 42.
The water rod 42 provides a low resistance flow path and potentially slightly cooler flow path to direct coolant to an upper elevation of the assembly 40 at the discharge end 46 of the water rod. The lower section 48 of the water rod 48 is a narrow diameter cylinder having an open end inlet 50 or side inlet ports 52 (side inlet ports may also be arranged on the side of the lower section 46 of water rod 42). Coolant enters the open end inlet 50 or side inlet ports 52 and flows up through the narrow lower section 40 and to a wide diameter upper cylindrical section 54 of water rod 44. The open end inlet 50 may be a few inches (a few centimeters) or a foot or more (0.3 meters or more) above the lower tie plate 16. Coolant enters the inlets 50, 52 of water rod 44, flows from the narrow section to the wide section 54 and discharges from the water rod at the discharge end 46.
The water rods 19, 42 and 44 have upper ends 34, 46 that do not attached to an upper tie plate. Accordingly, the water rods do not require upper end plugs to connected the rod to the upper tie plate. Because the upper (and optionally lower) tie plates do not require receivers for the water rods, the tie plates may be designed without the constraints of such receivers, e.g., threaded or smooth apertures to receive the end plugs of the water rods. Further, the water rods disclosed herein may be used to reduce the number of unique water rods needed for various fuel bundle assemblies in a BWR core 1 (which is not shown to scale in
By way of contrast, conventional BWR cores may have bundles of slightly differing lengths, e.g., BWR ⅔, BWR 4/6, etc., and these bundles require water rods of various specific lengths to accommodate the variations in length of the different fuel bundle assemblies. Because the water rods disclosed herein do not attach to the upper tie plate, a standard length water rod(s) may be used in the fuel bundle assemblies, despite the length variations of these assemblies.
The elimination of the upper portion of the water rods reduces the pressure drop of the fuel bundle assembly when compared to traditional designs by increasing the available cross sectional area within the channel 20 for coolant flow. The reduction in pressure drop and flow restrictions through the fuel bundle assembly may be especially beneficial for natural circulation BWR's.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not to be limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
