Abstract: An improved corrosion resistant ductile modified zirconium alloy for extended burnups in water-moderated nuclear reactor core structural components, fuel cladding and analogous corrosive environment uses is provided. It comprises:measurable amounts of niobium in a range up to 0.6 percent by weight, measurable amounts on antimony in a range up to 0.2 percent by weight, measurable amounts of tellurium in a range up to 0.2 percent by weight, tin in the range 0.5 to 1.0 percent by weight, iron in the range 0.18 to 0.24 percent by weight, chromium in the range 0.07 to 0.13 percent by weight, oxygen in the range of from 900 to 2,000 ppm, nickel in an amount less than 70 ppm, carbon in an amount less than 200 ppm and the balance zirconium and minor amounts of impurities.The alloy structure is substantially alpha phase with some precipitated second phase particles which are preferably within the size range of 1200 to 1800 angstroms.

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 bolt insert 24 with special bolt 50 provides a fastening method to secure hard metal nuclear reactor parts 12, 14, 16 provided with aligned square EDM produced openings 18, 20, 22. The insert is an elongated square internally threaded member with slots 34 defining flexing fingers 36. Fingers 36 have work engaging shoulders 42. Stop means tabs 28 at the bolt head end prevent overinsertion of the square insert 24 during the operation of pushing it into aligned square holes 18, 20, 22. Internal threads 32 of insert 24 mate with bolt threads 60 during torquing on bolt head 52 to advance bolt 50, which has tapered end 56 and pilot portion 58, to cam fingers 36 into holding position. Couterbores 30 receive stop means tabs 28 such that bolt head 52 does not bottom on insert 24. The method of producing fastening 10 removes the need for accurate threading operations on irradiated parts in the remote field.

Abstract: A tool having a rotating mast assembly 12 is provided which includes a hollow conductive gas transmitting electrode 14 and a non-hygroscopic ceramic shielding tube 12 which is made of at least 94% by weight Al.sub.2 O.sub.3 and has a tensile strength of at least 20,000 P.S.I. and an ability to withstand temperatures in excess of 1500.degree. C.

Abstract: A multisectioned nozzle dam (30) for use in a steam generator (24) with an integral bolt ring (32) has a body structure of general circular shape. Redundant seals including at least three separate inflatable peripheral seals (48, 50 and 52) with an alarm (A) for indicating a pressure increase between the second and third seals (50 and 52) is provided. Redundant supports including a plurality of independent bars (60, 62, 64 and 66) bolted to the integral bolt ring (36) secure the dam (30) within the nozzle (26) to the appropriate axial position.

Abstract: A fuel assembly has a spring detent spacer grid of intersecting strips for capturing and retaining deleterious debris carried by reactor coolant before it enters the active region of a fuel assembly. A plurality of fuel end caps are peripherally grooved to receive springs projecting from the strips. The end caps are thus captured by springs and debris is wedged and trapped on opposite sides of the strip and against the end caps by pairs of adjacent integral leaves projecting from the stips intermediate and substantially symmetrically arranged about their intersections.

Abstract: A nuclear fuel support grid 10' of egg-crate structure has wave defining strips 12a, 12b, 12c, 12d defined by bends 16' inclined from the vertical and opposing cantilevered springs 18' with inclined spring bases 20' opposing them for support of fuel rods 22 intermediate their ends. The "inclined waves" defined by inclined surfaces formed by bends 16' and spring bases 20' of cantilevered springs 18' provide lateral components to the coolant flow in patterns which enhance DNB and corrosion behavior.

Abstract: A tamper-proof closure 10 is inserted by means of positioning tool 20 into a nuclear fuel consolidation storage canister 30. The closure 10 includes a grooved weakened portion 44, which if it exceeds its elastic limit when the base 12 is flexed during removal attempts will indicate any attempts to remove or otherwise tamper with the thus closed canister. Locking tabs 18, on transverse legs 13 and 14 extending from base 12 are engaged in slots 40 in the wall of the opening of canister 30 when the closure 10 is in fuel storage position. Tool 20 has a portion 46 which enters a slot 48 in base 12 at 90.degree. to its working position and then twists to engage spanning portion 42's flanges 43 in slots of flanges 16 on the legs 13 and 14 to retract tabs 18. The base is prevented from flexing on insertion into the container opening by support it receives from portion 46.

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: An element basket assembly (30) for a rotary regenerative heat exchanger (2) is comprised of a plurality of heat transfer element plates (32) stacked in an array within a supporting basket frame formed of upper and lower plank-like shell members (34,44) each formed into a trough-like member having a base end (342,442) and a pair of spaced outwardly extending legs (344,444). The shell members (34,44) are interconnected at their base ends by corner angle bars (35) and at the outward ends of their legs by closure member (36) to form a four-sided frame housing. Retaining grates (42a,42b) are mounted within the trough-like shell members (34,44) so as to extend across the upper and lower end surfaces of the stacked element plates (32) for retaining the element plates within the housing.

Abstract: An apparatus 10 is provided for supplying a high-velocity flow of temperature regulated air 5 to the calender roll 90 of a paper making machine. Ambient air 1 is received into the plenum chamber 20 and distributed therefrom through a longitudinally elongated conduit means 30 which has an inlet 32 opening directly into the plenum chamber 20 and an outlet opening 36 along the other end thereof and defining therebetween a flow passageway 34. The outlet opening 36 is adapted to direct the air flow passing through the flow passageway 34 along the calender roll 90 in counter direction to the rotation of the calender roll 90. A series of spiral wound heating element coils 40 are disposed within the conduit means 30 at longitudinally spaced intervals along the length thereof to heat the air to a desired temperature by selectively powering the heating element coils 40.

Abstract: A welding apparatus (10) for longitudinally traversing and circumferentially welding within the interior of a tube. A rotating weld tip and gas supplying containing head is mounted on and rotationally driven by a rotor tube (36) extending from the end (90) of a cylindrical housing (12) in which it is mounted. The axially fixed rotor (36) is surrounded by and is driven by a helix drive connection (52,54,56) to a piston (20). The piston (20) reciprocates in a cylindrical bore (14) within the housing (12) in response to selectively applied fluid pressure acting against a spring bias (26). A strain gage (72) on the spring (26) controls the fluid pressure by means of valve ("V") whereby reciprocation of the piston (20) rotates the rotor (36) by means of the helical groove (52) and balls (54). The various parts are hollow to accommodate the necessary wire conductors (70,86) and gas flow.

Abstract: A wear-reduction-sleeve for in-core-instrumentation thimbles of a pressurized water nuclear reactor having bottom mounted instrumentation to curtail flow induced excitation and increase support contact area in the region of thimble length which extends through and defines an annulus with the core support plate and extends upwardly to and through the fuel assembly flow distribution plates. The wear-reduction-sleeve includes a hollow shank portion which gives a low wear coefficient when in contact with the chrome-plated thimble and is inserted into the annulus and below where it is radially expanded and secured to a thimble guide tube. An upper portion of the wear-reduction-sleeve between the core support plate and flow distribution plate has a flow collection chamber and radial flow exit slots which divert thimble flow substantially away from the hole in the fuel assembly flow distribution plate through which the thimble extends.

Abstract: A two-speed stepper actuator (10) for rotationally driving a power nut (24) to adjust a slice lip spindle (20) linearly. A clamp for power nut (24) includes a bushing plate (32) driven by drive solenoid (D) which is mounted for rotation relative to power nut (24). A lever (40) is pivotally mounted on the bushing plate (32) and includes an eccentric locking cam surface (50) shaped for selective clearance of nut (24) when in the center or number 2 position and clamping engagement of nut (24) when in the opposite extreme 1 and 3 positions. A first amount of rotation of the lever (40) about its pivotal mounting (48) on said bushing plate (32) engages and locks lever end cam surface (50) against nut (24) and a second and additional rotation of the lever (40) then drives the nut (24). Three position solenoids (L) and (D) drive the bushing plate (32) and lever (40) independently and at different speeds due to an accommodation by spring (36) on pusher rod (34) of solenoid (L).

Abstract: A tool 10 for creating a standard repeatable impact on a nuclear steam supply system (NSSS) structure to determine the response of an accelerometer to the impact of a known energy at a predetermined location on the structure. The tool 10 includes a barrel 12 and a spring 30 which biases a ram 20 reciprocally mounted in the barrel and driven by cam plates 66 and 68 on shaft 60. A flange 28 on ram 20 compresses spring 30 and upon movement of follower 72 to a maximum radial distance from shaft 60, the follower 72 drops down step 70 on the cam surface to allow spring 30 to uncompress and project ram 20 out of the barrel such that end 22 of the ram creates a standard impact on the NSSS structure. A hand crank drives shaft 60. A dampening spring 78 assists in the rebound of the ram 20.

Abstract: The printability of paper coated with kaolinite clay is dependent upon the flatness of kaolinite alumino-silicate clay platelets on the surface thereof. The flatness is determined by calculating the ratio of two infrared absorption bands from two specific types of structural hydroxyls characteristic of kaolinite clay platelet crystals.

Abstract: A method of repairing leaky compression fitting seal joints between a pressure stub tube (22) projecting from a nuclear reactor head (12) and a cylindrical thermocouple body (24) concentrically mounted in the stub tube (22) for penetration of the reactor pressure boundary. The method includes the steps of loosening and disassembling compression fitting nuts (30,32) and fitting body (34) to expose, and remove by grinding, a cammed ferrule radial compression means (26,28), cleaning the surfaces to be sealed, axially telescoping a split collar (40) between the tube (22) and the thermocouple body (24) and providing split rings (44,46) of brazing material surrounding the thermocouple body adjacent the exposed ends of the tube (22) and the collar (40). Resistance heating the tube and, therefore, the brazing material and repositioning and reassembling the fitting body (22) and fitting nuts (30,32) to complete the repaired seal joint.

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: An arrangement for temporarily sealing the space between two substantially parallel, adjacent plates in which a flexible, partially inflatable seal is located between the plates to effect primary and secondary sealing interfaces along the upper and lower edges of the plates, respectively. The seal has a wedge-shaped upper portion, a tubular lower portion and a substantially solid intermediate shank. The tubular end of the seal is inflated so that it expands into contact with the lower edges of the plates, drawing the wedge-shaped upper portion of the seal toward the tubular portion, thereby forming primary sealing interfaces between the wedged-shaped portion and the upper edges of the plates. The contact of the inflated tubular portion with the lower edges of the plates forms secondary seal interfaces. The effectiveness of the seal can be tested by measuring the pressure in the chambers formed between each set of primary and secondary sealing interfaces.