referring now to the drawings , there is shown in fig1 a nuclear reactor fuel assembly 10 comprising an array of fuel rods 12 held in spaced relationship with each other by support grids 14a spaced along the fuel assembly length . each grid includes a peripheral strap 20 . in assembling a fuel assembly , an array of control rod guide tubes 15 having control rods 40 adapted for slidable longitudinal movement therein , are positioned to extend axially through selected cells in the grid and are thereupon welded to grid tabs or strap walls to form the fuel assembly skeleton structure . opposite ends of the guide tubes are attached to top and bottom nozzles 42 , 44 in the usual manner . referring now to the portion of the prior - art support grid 14 shown in fig2 upper and lower straps 22 , 23 made of zircaloy , inconel or other material are interwoven to form grid sections of egg - crate configuration . the three support grids 14 shown in fig1 are vertically aligned such that the square - shaped openings 24 formed by the interwoven straps 22 , 23 are likewise vertically aligned to form cells that are of a size sufficient to receive fuel rods 12 or control rod guide tubes . each square - shaped opening 24 designated to receive a fuel rod 12 has a pair of arches 25 on two adjacent sides and a pair of spring tabs 26 on the remaining opposing adjacent sides . the cells formed from the vertically - aligned square - shaped openings 24 within the support grids 14 thus contain adjacent , vertically aligned columns of arches 25 and spring tabs 26 which are disposed for contact with the fuel rods 12 . note that only lines of contact 27 are formed between the fuel rods 12 and the arches 25 and spring tabs 26 . fig3 illustrates a portion of a support grid 14 which is designed in accordance with an embodiment of the present invention . as can be seen from fig3 this improved support grid 14 is equipped with improved spring tabs 26a and arches 25a which follow the contour of the circumference of the fuel rod 12 , thereby providing substantially arc - shaped areas of contact 27a between the fuel rod 12 and the arches 25a and spring tabs 26a . obviously , contact area can be further increased by further increasing the length of the arc along which the arches 25a and spring tabs 26a follow the circumference of the fuel rod and by increasing the width ( i . e ., the dimension normal to the paper in fig3 ) of the arches 25a and spring tabs 26a . previously published research indicates that metal wear ( as measured by material volume removed ) is proportional to load , with the area of metal contact essentially having no effect on the material volume removed . see . archard , j . f ., and hirst , w ., &# 34 ; the wear of metals under unlubricated conditions &# 34 ;, proc . royal society ( london ), vol . 236a , pp . 397 - 410 ( 1956 ). thus , by holding the contact force between the fuel rod 12 and the support grid 14 approximately constant and by increasing the contact area over which the material will be removed , the depth of any fuel rod fretting wear will be reduced since the wear is distributed over a larger area . moreover , when gaps arise between the fuel rod 12 and arches 25a and spring tabs 26a ( e . g ., due to interactions between the fuel rod 12 and support grid 14 under reactor operation conditions ) the contoured shape of the support grid arches 25a and spring tabs 26a will dampen destructive vibrations between the fuel rod 12 and arches 25a and spring tabs 26a due to the enhancement of squeeze film effects between these elements . by dampening vibrations , impact loads are lessened and fuel rod 12 wear is reduced . squeeze film behavior is characterized by a large buildup of force which occurs just prior to impact and which acts in a direction to reduce the impact . research in this area , based on tube vibrations within an annular support , indicates that the increase in damping due to the squeeze film effect increases with the velocity of the vibration . such damping should also increase with increasing the area of contact on impact , as suggested by the observation of a decrease in squeeze film effects upon tube canting ( which causes point contact , rather than line contact ) and by an increase in squeeze film effect with the length of contact area ( i . e ., support &# 34 ; thickness &# 34 ;). see , haslinger , k . h ., and martin , m . l ., &# 34 ; experimental characterization of fluid and squeeze film effects in heat exchanger tube supports &# 34 ;, journal of fluids and structures , vol . 4 , pp . 605 - 629 ( 1990 ). finally , the contoured shape of the arches 25a and spring tabs 26a provides additional resistive force during lateral loading ( e . g ., effects due to seismic activity , loca , operating , shipping , and so forth ). this is due to the fact that , as the fuel rod 12 moves laterally , the spring tabs 26a deflect a greater distance due to their contoured shapes , producing larger relative forces . of course , in using contoured arches 25a and spring tabs 26a such as those shown in fig3 assembly considerations such as potential mixing vane interferences should be taken into consideration . fortunately , spacer grid assembly fixtures are available which have mixing vanes that can be held out of the way during assembly so that such interferences will not exist . thus , a support grid 14 for a nuclear reactor fuel assembly 10 has been described which includes contoured spring tabs 25a and arches 26a for increased contact area with nuclear fuel rods 12 . such increased contact area is provided to remove fuel rod fretting and to increase resistive forces during lateral loading . from the foregoing description , one skilled in the art can easily ascertain the essential characteristics of this invention , and without departing from the spirit and scope thereof , can make various changes and modifications of the invention to adapt it to various usages and conditions .