Fuel assembly spacer grid with swirl deflectors and hydraulic pressure springs

A fuel assembly spacer grid for a nuclear reactor comprising a plurality of longitudinally-extending, parallel, spaced vertical straps, and a plurality of laterally-extending, parallel, spaced vertical straps perpendicularly interconnecting the longitudinally-extending straps, the interconnecting straps supporting at least one fuel element of a nuclear fuel assembly, further comprising:

• a plurality of interior interconnections each formed about an axis at the interconnections of the interconnecting straps and the interconnections having an upper end;
• a plurality of swirl deflectors each respectively arranged at an interior interconnection on the upper end of the interconnections, the swirl deflector comprises a pair of interconnecting substantially triangular base plates extending upwardly from a respective strap, each triangular base plate comprises a base on the strap and a side surface extending upwardly at an obtuse angle from the base on each of the respective strap toward the axis and a pair of vanes attached to each side surface of each substantially triangular base plate wherein the vanes are bent at an angle to the base plate to have an air vane shape;
• and
• a spring in a fixed state at one end thereof while being in a free state at the other end thereof, the spring having a curved contact portion arranged between the ends thereof, the curved contact portion being in surface contact with a circumferential surface of a fuel element supported thereby, and the spring being configured to utilize, as a spring force, a hydraulic drag force generated when a cooling water flow passing through the spacer grid comes into contact with a bent portion at the free end of the spring, the bent portion being inclinedly bent with respect to a flowing direction of the cooling water flow in such a manner that it has a larger area at an upper portion thereof than that at a lower portion thereof wherein the spring force of the spring varies with the cooling water flow such that an increase in cooling water flow rate increases the spring force so as to support the fuel element more firmly.