Patent Number: 040594840
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENTS Referring now to the drawings wherein like parts are designated by the same reference numeral throughout the several views, FIG. 1 illustrates an elevational view of a reload 17 .times. 17 fuel element assembly 10 for pressurized water reactor (PWR), of the type to be used in locations where there are no control rods, comprising a typical square transverse cross-section and provided with a plurality of nuclear fuel rods 12 arranged in parallel array, an upper tie plate 14, a lower tie plate 16, and fuel element spacer devices 18 and 20 which are disposed along the length of the fuel assembly for maintaining the fuel rods in fixed spaced relation, i.e. pitch, minimizing vibration and promoting flow mixing between fuel rods within individual assemblies and between adjacent assemblies. The fuel assembly includes the usual instrument tube 22 which provides in-core bottom access to the neutron detectors therein. Also provided are the usual control tubes 24 which are structural members which may provide receptables and guide surfaces for assembly control rods. The tubes differ in number depending on the particular fuel assembly design. FIG. 2 shows a transverse cross-section of the fuel assembly of FIG. 1, clearly illustrating the fuel arrangement utilized at core locations where there are no control rods. Each fuel rod 12 comprises an elongated tube containing a fissile fuel material such as enriched uranium dioxide UO.sub.2. The rods are supported in the usual manner at their lower end by the lower tie plate 16, and at their upper end, they are supported laterally only, by the top spacer adjacent to the upper tie plate. The control rod guide tubes serve as the structural skeleton for the fuel assembly and provide guidance for the control rod cluster which is inserted from above to control reactor power. FIG. 3 illustrates the hybrid fuel assembly configuration of the present invention by showing a top view of the spacers. While the preferred embodiment is in a 17 .times. 17 fuel array with islands of 4 .times. 4 fuel rod island clusters wherein the latter fuel rods are positioned on the same pitch as in a 15 .times. 15 fuel assembly, the invention also is applicable to and has utility with other nuclear reactor fuel designs such as 16 .times. 16 fuel assemblies as will be apparent from the following description. The spacer device 18 essentially comprises intersecting grids on support strips which form an egg-crate with openings 26 through which the fuel rods 12 pass. As shown located symmetrically about the intersecting diagonals and with respect to each diagonal per se and in each quadrant of the assembly, there are provided four islands 28. Each island may be identical in construction and employ the same nuclear fuel rod design (i.e., size and pitch) that would be employed for a standard 15 .times. 15 fuel array or the size and pitch can be suitably modified from that normally used in a standard 15 .times. 15 array for use in the island area. By locating these islands within the matrix of 17 .times. 17 fuel, retention of the control rods normally employed in a 15 .times. 15 fuel is enabled, while the maximum LHGR typical of the 17 .times. 17 fuel is achieved. Thus, as illustrated in FIG. 3, there are 188 fuel rods having a 0.380 inch diameter whereas normally there would be 280 such fuel rods in the 17 .times. 17 fuel array. Each of the fuel rods is held in place by dimples 30 and springs 32 which extend inwardly into each of the nuclear fuel rod openings formed in each spacer. The normal 17 .times. 17 array has been replaced by 16 guide tubes 34 and a corresponding number of control rods 36, all of which are disposed within each of the islands 28 as discussed in detail hereinafter. The dotted lines in FIG. 2 illustrate those portions of the 17 .times. 17 array which have been removed and replaced by the islands 28 in accordance with the present invention. As illustrated in FIG. 2, 25 locations or openings 26 have been replaced by each island. An island 28 essentially comprises a module having sides 38 and intersecting strips 40 and 42, which form an egg-crate having naturally larger openings 44 for receiving the respective fuel rods and guide tubes. These openings accommodate larger size fuel rods 46, making forty-eight in number in the assembly (each has 12 rods), of 0.470 inch diameter. The rods 12 and 46 contain different fuel enrichments in order to lower power production in the large size rods, thereby maintaining their LHGR reasonably close to that of the small size rods. Each module is structurally similar in all respects to the grid spacer of the 17 .times. 17 fuel array for purposes of maintaining the fuel rods and guide tubes in place. Each module 28 includes four guide tubes 34 having a corresponding control rod 36, which replace two guide tubes and control rods of the 17 .times. 17 fuel assembly shown in FIG. 2. It should be understood that FIG. 2 does not illustrate a typical 17 .times. 17 assembly. A normal 17 .times. 17 assembly has 20 or 24 guide tubes to accommodate the control rods appropriate for 17 .times. 17 arrays. FIG. 2 employs a minimum number of guide tubes (eight) to satisfy structural requirements only. The guide tube and control rod arrangement in each island may be the same as that for a 15 .times. 15 fuel array or suitably modified for the particular fuel design. By so constructing a 17 .times. 17 fuel array with islands of fuel rod clusters, compatability is retained with control rod clusters which were designed for insertion into the 15 .times. 15 assemblies. By using a hybrid assembly in accord with the teachings of the present invention, in a PWR the water content is distributed in the region of the control rods more uniformly because the larger hydraulic diameter in the four 4 .times. 4 islands balances the flow channelling which occurs between assemblies. The hybrid assembly when associated with an appropriate enrichment distribution, enables reduction of the maximum LHGR by about 20 to 25 percent, which means a reduction of from about 171/2 KW/ft. to 13-14 KW/ft. A typical enrichment distribution that would satisfy the above is where one-half of those reload assemblies which replace the original fuel assemblies, FIG. 2 (Type A assemblies) have an assembly average enrichment of approximately 0.3% higher than the normal reload enrichment, while the other half of the reload assemblies have an assembly average enrichment of approximately 0.3% lower than the normal reload enrichment (Type B assemblies, FIG. 3). This permits further reductions in relative assembly power peaking in the core. The lower enrichment reload assemblies are provided in the regions of normally higher power (i.e. away from core periphery and locations adjacent to fuel with relatively high reactivity so that a flatter power distribution is achieved, thereby reducing the peak assembly heat generation rate). The reduction of island fuel rod enrichment enables dropping the power in the island rods so that the desired low LHGR is obtained. With such an enrichment distribution the local power peaking in the hybrid assembly will be higher than that in a uniform 15 .times. 15 or 17 .times. 17 or other uniform rod fuel assembly. However, the peak power in the hybrid assembly still occurs in the portion of the fuel assembly externally of and at the periphery of the islands, which results in an acceptably low LHGR. The following tables are illustrative of some typical mechanical design characteristics and enrichments for a hybrid assembly in accordance with the present invention in a PWR. It should be recognized, however, that the present invention is applicable to types of power reactors where 16 control rods are used as in a 15 .times. 15 fuel assembly as well as in other fuel assemblies, for example, a 14 .times. 14 fuel array, 16 .times. 16 and 18 .times. 18 fuel arrays. TABLE I ______________________________________ Uniform* Hybrid Fuel Assem- Fuel bly (For Control) Assembly Rod Locations) Mechanical Type A Type B ______________________________________ No. Small Fuel Rods/Assembly 280 188 No. Large Fuel Rods/Assembly None 48 No. Guide Tubes/Assembly 8 16 No. Instrument Tubes/Assembly 1 1 Cladding Material Zirc-4 Zirc-4 Cladding O.D., in. 0.380 0.380 & 0.470 Cladding Thickness, inc. 0.024 0.024 & 0.030 Active Length, inc. 144 144 Total Fuel Rod Length, inc. 165.625 165.625 UO.sub.2 Per Assembly, lb. 1233 1076 ______________________________________ Average Linear Power Densities (KW/ft.) Type A Type B Small Large 17 .times. 17 Rods Rods ______________________________________ Thermal-Hydraulic (overall reactor) Average LHGR, KW/ft. 4.60 5.22 5.60 Maximum LHGR, KW/ft. 12.23 12.23 14.00 Nuclear Total nuclear peaking factor 2.57 2.26 2.42 Total heat flux peaking factor 2.66 2.34 2.50 Average Reload Enrichment Enrichment wgt. % U.sup.235 3.22 2.88 1.75 .BHorizBrace. 2.65 avg. Average Reload Enrichment 2.94 ______________________________________ *To be kept away from control rod positions at all times. FIG. 5 shows the fuel enrichment distribution in transverse cross-section of one quadrant of a fuel assembly in accordance with the present invention. The remainder of the assembly would have symmetrical fuel enrichment with respect to the centerlines of the assembly. Thus, in the 17 .times. 17 assembly with 4 .times. 4 islands which have fuel rods 12 and 46, respectively having different fuel compositions and different sizes, the smaller size rods 12 are located externally of the islands and at the periphery of each assembly are designated M and comprise high enrichment uranium oxide containing 2.88% by weight U-235 and having an outside diameter of 0.380 inches. On the other hand, the rods in the islands 28 are designated L and contain low enrichment uranium oxide containing 1.75% by weight U-235 and have an outside diameter of 0.470 inches which avoids excessive flow area in that region. The four locations within each island designated RCC actually comprise the guide tube 34 and control rods 36. FIG. 5 provides the nuclear beginning of life characteristics of the fuel by illustration of the enrichment distribution for the hybrid fuel assembly containing fuel rods of two different diameters. This is by comparison to the uniform enrichment distribution which normally would be found in the 17 .times. 17 fuel assembly having uniform size rods throughout. FIG. 6 illustrates the relative volumetric power distribution for a quadrant of a hybrid fuel assembly in accordance with the present invention. In the hybrid arrangement the large size rods (in the islands) produce about 21.45% of the power while the small size rods produce 78.54%. As shown, maximum power peaking in the assembly occurs outside the island and the minimum power peaking is in the islands. FIG. 7 illustrates the local relative linear heat rate for a quadrant of a hybrid fuel assembly in accordance with the present invention. To determine absolute linear heat rate, the local relative linear heat generation rate given in FIG. 7 is multiplied by the average linear heat generation rate for the bundle. This illustration is prepared in accordance with standard practice in the art from FIG. 6 which provides the local peaking component used in determining maximum linear heat rate. One can easily determine the relative linear heat rate indicated in each of the block spaces which corresponds to the fuel rods 12 and 46 in the fuel assembly of FIG. 3. The hybrid fuel assembly incorporation of islands of fuel rod clusters provides a relatively unique flow distribution advantage. Thus, while there has been described heretofore and illustrated herewith a preferred embodiment of the present invention including various modifications and variations thereof, still further modifications and variations thereof will be obvious to those skilled in the art once they have been made aware of the present disclosure. For example, the invention may have utility with other types of fuel design and arrangements. Accordingly, reference should be made to the following appended claims to determine the true scope and spirit of the subject invention.