Abstract: A strip (16) for an eggcrate-type nuclear fuel assembly grid (10), in which the fuel rod support springs (30,36) are formed by beams (75,77) and a connecting arch (78). More particularly, the strip has a substantially flat body (56), upper and lower edges (84,86) defining the strip vertical height, and opposed side edges (80) defining the length of the body. The fuel rod support structure (30) projects transversely from the body and comprises a plurality of spring members spaced apart in the longitudinal direction along the body, each spring member having a pedestal portion (75,77) resiliently supported by the body and a contact portion (78) integrally formed on and projecting from the pedestal portion. The pedestal portion preferably includes a beam integrally constrained at both ends by the body. By integrally fixing the ends, the spring member can be considerably smaller and produce the same force for a given deflection as a conventional grid.

Abstract: An improved lower end fitting (L.E.F.) having a bell mouth type of flow jet diffuser decrease pressure drop 10-15%, more evenly distributes flow and adds strength. It includes neutron thimble flux impingement shield of instrument and/or cable. Diffusers are stainless steel of circular cross-sect. and parabolic to optimize diffusion. Shape is based on lower core plate flow hole geometry, L.E.F. design and reactor flow rate. Thinner L.E.F. legs, smaller L.E.F. gussets and thinner L.E.F. flow plates possible.

Abstract: Pressurized water reactor fuel bundles (10) have a cast lower end fitting (20) which provides reduced pressure drop because nozzles (24) are of polygonal (rectangular or square) cross-section and the flow entrance wall portion (32) is a parabolic shape which merges into a wall portion (30) parallel to the flow direction. The parabolic shape of portion (32) and fillets (24a) at the nozzle (24) corners also give an improved draft to the casting. Pressure drop reduction was substantially greater than standard calculations indicated would be obtained.

Abstract: A cantilevered hold-down spring (68) for a nuclear fuel assembly (10), comprising an elongated metal bar including a substantially straight long leg portion (66) having one end adapted to be mounted (38) to a fuel assembly, an arcuate transition portion (70) at the other end of the long leg, and a straight short leg portion (76) extending from the transition portion at an acute included angle with the long leg portion, and a load transfer means (64) projecting from the straight leg intermediate the transition portion and the long leg first end. As the load on the primary loading point (80) on the transition portion increases, the load is transferred to the projection (64), thereby effectively shortening and stiffening the spring.

Abstract: A pressurized water reactor fuel assembly (10) has a fastener or bolt (40) of stainless steel with a longitudinal groove (48) attaching zircaloy guide tubes (16) to stainless steel lower end fitting (14). The guide tubes have internally threaded zircaloy plugs (52) for mating with the threads (46) of bolt (40) with points (50) created in the threads (46) by groove (48) providing increased friction. The groove (48) acts to accommodate stresses set up by differential thermal expansion of zircaloy and stainless steel. Apertured stainless steel cups (60) receive the plugged ends of guide tubes (16) to capture them and provide connections to lower grid (22) of stainless steel.

Abstract: A fuel element for a nuclear reactor having a zirconium-tin alloy cladding tube, with a thin coating of particles of enriched boron-containing compound burnable poison particles, deposited from a liquid sol-gel which includes a glass binder material.

Abstract: A fuel assembly (10) has a lower end fitting debris collector and end cap spacer grid (20) assembled in the form of a welded assembly of an "eggcrate" grid (21) and cast base (40) with hollow legs (42). Fastener seats (46) in hollow legs (42 ) permit guide tubes (14) with internally threaded ends to be joined to the upper surface of the lower end fitting debris collector (20) by means of slotted fasteners (50). End caps (22) rest on grid (21) at the intersection of slottedly interlocked bars (24 and 26). Thin strips (30) mounted in slots between bars (24) and bars (26) provide small debris catching openings in grid (21). Thick strips (30a) project upwardly between strips (30) to limit lateral movement of the end caps. Projections (70) on bars (24) prevent axial fuel rod movement by engagement of tab (70a) in circumferential groove (23) of end caps (22). Opposing capture force is provided by a wire (72) which is supported in openings in thick strips (30a) and which is received in groove (23).

Abstract: A wear-reduction-shield (40) for use between the core plate (24) and lower end fitting (26) of a pressurized water reactor (10) to reduce excessive wear of in-core-instrumentation thimbles (30) due to flow induced vibrations and resist fuel assembly tipping has a cylindrical body portion 42with core plate engaging lower end surface (44). At the opposite and upper end, a tapered internal end wall (46) assists upward threading of the monitor and cable. On the outside of the upper end symmetrical leg portions (52) and central land (54) surround a thimble (30) receiving opening (48). Smoothly tapering outer surface (56) minimizes turbulence in and beyond opening (34) in lower end fitting (26). Internal dimensions of shield (40) avoid structure such as sleeve (50) which may be present.

Abstract: A fuel element for a nuclear reactor having a zirconium tin alloy cladding tube, with a thin coating of enriched boron-containing alloy burnable poison, such as nickel-thallium-boron deposited from a reducing agent by an electroless plating process.

Abstract: Integral vanes 4 with optimized size, shape and bend angles maximize coolant mixing and fuel rod 12 heat transfer downstream. Recessed weld nuggets 5 with no vane cutout are optimized for size, strength and corrosion resistance. Staggered arches 20',22' and springs 20,22 minimize turbulence and reduce grid pressure drop and promote coolant mixing. Crowned arches 20',22' and springs 20,22 decrease scoring of fuel rods 12 and are sized to minimize turbulence and pressure drop. Minimum cutouts in unslotted section of grid strip 46,46' give 15-20% strength increase. Intermediate weld and tapered end slots 48 give 15% strength increase. Ribbed and round dimple stiffeners 38,39 on outer strips increase buckling resistance, reduce handling damage and spreads accidental loading. Outer strips 32 are optimized for strength, handling, turbulence generation and pressure drop. They also divert enough flow to interior of fuel assembly to match thermal power distribution and eliminate fuel rod corrosion concerns.

Abstract: A fuel assembly (10) has a lower end fitting debris collector (40) assembled in the form of a welded assembly of an "eggcrate" grid (21) and cast base (40) with hollow legs (42). Fastener seats (46) in hollow legs (42) permit guide tubes (14) with internally threaded ends to be joined to the upper surface of the lower end fitting debris collector (40) by means of slotted fasteners (50). Bevels (62) and notches (64) in the grid bars (26 and 24a, respectively), provide an embodiment with contoured seats for fuel rod end caps (22). Otherwise, end caps (22) rest on grid (21) at the intersection of slottedly interlocked bars (24 and 26). Thin strips (30) mounted in slots between bars (24) and bars (26) provide small debris catching openings in grid (21).

Abstract: A hollow flow deflector (10) for use in a nuclear reactor fuel assembly having spaced grids of orthogonal strips (16, 18) mounted for defining square matrices of aligned and supported cylindrical fuel elements (12, 14). The deflector has a central cylindrical opening (20), an upstream end portion (22), a downstream end portion (24) and an intermediate transition portion (26) joining the end portions. The hollow flow deflector (10) has a plurality of concave flow channels (30) regularly spaced about the periphery of the body in its downstream end portion. The flow channels (30) have their inlet portion defined in the transition portion (26) of the body (10).

Abstract: A debris trap is mounted within a bottom nozzle of a fuel assembly so as to capture and retain debris carried by coolant flowing from the lower core plate openings of the nuclear reactor to the fuel assembly. The trap includes a hollow enclosure disposed below the adapter plate of the bottom nozzle and between the corner legs of the nozzle. The enclosure is composed of upper and lower walls and a continuous side wall which spaces apart the upper and lower walls and interconnects their peripheries so as to form a debris capturing and retaining chamber within the hollow enclosure. The walls are composed of a material, such as wire mesh screen, which is permeable to liquid coolant but impermeable to debris. A plurality of wall sections severed from the lower wall and bent into the chamber of the enclosure define a plurality of openings into the chamber.

Abstract: A grid for a nuclear reactor fuel assembly which includes two sets of interwoven straps which form square openings of egg-crate configuration. One set is placed on top the other with the openings in alignment to receive fuel rods. The vertically aligned square openings thus constitute single cells through which fuel rods are adapted to extend. The top edges of straps in the bottom grid are provided with narrow slots which extend in multiple rows diagonally across the grid when the straps are assembled. A spring, one for each row of diagonal slots, is threaded through the slots before the top grid is set in place. Each single cell contains two pairs of vertically spaced dimples on adjacent walls of the straps as in conventional construction. That portion of the spring, which extends through each cell, engages a side of the fuel rod in the cell and urges it into contact with the dimples, thus providing five points of support for each fuel rod which extends through the cells.