Apparatus and methods for pet waste disposal include using a portable waste collection receptacle disposed on a handle. A heat source is mounted together with the waste collection receptacle, capable of incinerating waste disposed in the waste collection receptacle.

A clamp for a tensile implement and method of clamping a tensile implement is disclosed. The clamp is portable and adaptable to different sizes of tensile implements. The clamp includes a cavity defined by side surfaces of a pair of blocks which are attached to a top surface of a grip base. A pair of mated reciprocal wedges, selected based on size of the tensile implement from a plurality of pairs of wedges, fits and slides within the cavity in order to grip the tensile implement. Each one of the wedges has a planar surface for sliding and a semi-cylindrical void which forms a cylindrical void through which the tensile implement passes when fully clamped around the tensile implement.

A jointed mechanism including a segment coupled to a joint; and an elongated component coupled to the segment, where applying a pulling force to the elongated component rotates the segment around the joint, elastically deforming the elongated component; wherein the elastic deformation generates an elongated component elastic force sufficient to rotate the segment, in an opposite direction, in absence of the pulling force.

A vacuum-lifting device includes a holding block and a nozzle. The holding block defines a holding hole and a threaded hole communicating with the holding hole. The nozzle includes a first section that is slidably received in the holding hole and a second section. The second section extends from the first section and has an outer diameter smaller than an outer diameter of the first section.

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.

According to an installation method of a water-chamber working apparatus of the present invention, the water-chamber working apparatus includes a base that holds heat transfer tubes on a tube plate surface and is fixed to the tube plate surface, and a manipulator that is coupled with the base, suspended in a water chamber and arranged therein, and has a separable configuration. In this case, a base installing step of installing the base on the tube plate surface and a manipulator coupling step of carrying the separated manipulator (a front stage and a rear stage) into the water chamber sequentially and individually and coupling the manipulator with the base (a coupling link) are performed.

Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

A method and apparatus for repairing and/or reinforcing a Boiling Water Reactor (BWR) jet pump riser pipe. The repair includes attaching two collars to the riser pipe using match drilling to drill holes through the collars and the riser pipe and plugging the holes with expandable plugs. Support columns are attached to the collars. Brace supports are slideably attached to the support columns. Gaps between each brace support and its respective collar are then narrowed as ratchet bolts may apply a force that pulls downward on an upper collar and pulls upward on a lower collar, thereby exerting a compression force on the riser pipe. A clamp assembly may also be located between the two collars that applies a hoop force on the riser pipe.

Textured surface for increasing Leidenfrost temperature. The texture comprises of surface features over multiple length scales—from micro to nanoscale—wherein the features at each length scale have a size, aspect ratio, and spacing selected to increase the Leidenfrost temperature. The structure includes an array of microscale structures disposed on the surface, the structure having size, aspect ratio and spacing selected to increase Leidenfrost temperature. The microscale structures may also include nanoscale structures on their surface to create a hierarchical structure. The structures result in an increased Leidenfrost temperature.

An apparatus for monitoring nuclear thermal hydraulic stability of a nuclear reactor, contains: a calculation unit configured to calculate a stability index of a nuclear thermal hydraulic phenomenon based on nuclear instrumentation signals, the signals being outputted by a plurality of nuclear instrumentation detectors placed at regular intervals in a reactor core; a simulation unit configured to simulate the nuclear thermal hydraulic phenomenon based on a physical model by using information on an operating state of the nuclear reactor as an input condition; a limit value updating unit configured to update a limit value of the nuclear thermal hydraulic phenomenon based on a result of the simulation; and a determination unit configured to determine, based on the stability index and the limit value, whether or not to activate a power oscillation suppressing device.

An aneutronic magnetron energy generator that generates microwave energy from a fusion-fission reaction that produces alpha particles in response to a proton colliding with an 11B nucleus. The magnetron energy generator includes a magnetron having an anode resonator including a central chamber and a plurality of radially disposed cavities. A cathode assembly is provided at the center of the chamber and includes a cathode electrode that generates a proton plasma. A series of electrically isolated acceleration rings extend from the cathode electrode and operate to accelerate protons from the proton plasma towards an outer target ring composed of boron eleven (11B). The accelerated protons fuse with the 11B nuclei to generate the alpha particles that then interact with crossed electric and magnetic fields between the target ring and the cavities. The alpha particles resonate with the cavities and generate a current within the resonator that is collected.

A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG.

A method and apparatus for securely fastening a pipe collar or a bracket to a riser pipe of a boiling water reactor (BWR) jet pump assembly. A pipe plug assembly includes an angled pipe plug that acts as a wedge to expand a bushing assembly as the pipe plug is drawn into the overall pipe plug assembly. Expansion of the bushing assembly allows a tight tolerance to exist between an outer diameter of the pipe plug and an inner diameter of the collar/bracket and riser pipe. Expansion of the bushing assembly allows a straight hole to be match drilled into the collar/bracket and riser pipe, thereby avoiding a more complicated tapered hole to be drilled into the collar/bracket and riser pipe. An ensuing tight fit between the pipe plug assembly, the collar/bracket and the riser pipe mitigates vibration of components and minimizes leakage to acceptable levels for use in the flooded environment of the annulus region where the jet pump assembly exists in the BWR.

A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.

A control rod/fuel support handling apparatus that is used in the case where a control rod and a fuel support are held, removed and lifted in a reactor and then are transported into the reactor in a periodical inspection of a BWR and in the case where the control rod and the fuel support are attached and mounted again into the reactor, the control rod/fuel support handling apparatus including: a fuel support gripper that holds the fuel support with a support gripping member; a control rod gripper that includes a vertically movable and rotatable elevating/rotating unit, holds the control rod with a control rod gripping member, disconnects and connects the control rod and a control rod drive mechanism, and allows removal and attachment of the control rod; and a control panel that controls automatically controls the control rod gripper in response to the instructions from an operation pendant.

A system, method and apparatus for providing additional radiation shielding to a ventilated cask for holding high level radioactive materials. The invention utilizes a tubular shell that is ancillary to the ventilated cask that circumscribes the ventilated cask to add radiation shielding protection while improving heat removal by natural convective air flow. Because the tubular shell and cask are non-unitary and slidably separable from one another, crane lifting capacity is not affected. In one aspect, the invention is an apparatus for providing additional radiation shielding to a cask holding high level radioactive materials comprising: a tubular shell extending from an open bottom end to an open top end, the tubular shell having an inner surface that forms a cavity about a longitudinal axis; a plurality of primary apertures forming passageways through the tubular shell and circumferentially arranged in a spaced-apart manner about the tubular shell; a plurality of secondary apertures forming passageways through the tubular shell and circumferentially arranged in a spaced-apart manner about the tubular shell; and an annular seal coupled to the tubular shell and extending from the inner surface of the tubular shell; wherein the secondary apertures are located at an axial height above the annular seal and the primary apertures are located at an axial height below the annular seal.

A lid frame for a nuclear fuel assembly shipping container and a shipping container for nuclear fuel assemblies are provided. The shipping container can include a lower container in which a cradle is installed, an upper container detachably coupled to the lower container, and a base frame coupled to the cradle with at least one nuclear fuel assembly placed thereon. The lid frame can include a plurality of supports installed apart from each other so as to surround the nuclear fuel assembly placed on the base frame, and a plurality of clamps separated from each other, coupled to the plurality of supports perpendicular to the plurality of supports, rotatably hinged to the base frame, and configured to clamp the nuclear fuel assembly. The lid frame safely protects the nuclear fuel assembly that is being transported.

A neutron generator includes an ion source disposed in a pressurized environment containing an ionizable gas. The ion source includes a substrate with a bundle of carbon nanotubes extending therefrom. The ends of the nanotubes are spaced from a grid. Ion source voltage supply circuitry supplies a positive voltage potential between the substrate and the grid of the ion source to cause ionization of the ionizable gas and emission of ions through the grid. An ion accelerator section is disposed between the ion source and a target. The ion accelerator section accelerates ions that pass through the grid towards the target such that collisions of the ions with the target cause the target to generate and emit neutrons therefrom. The ion source, accelerator section and target are housed in a sealed tube and preferably the carbon nanotubes of the bundle are highly ordered with at least 106 carbon nanotubes per cm2 that extend in a direction substantially parallel to the central axis of the tube. The neutron generator provides gas ionization at much higher atomic to molecular ratio that the prior art, which allows for small compact size designs suitable for logging tools that are used in space-constrained downhole environments.

Electrochemical corrosion potential (ECP) probe assemblies may be used to monitor ECP of materials due to coolant chemistry in an operating nuclear reactor. Example embodiment assemblies include at least one ECP probe that detects ECP of potentially several different materials, a structural body providing a fluid flow path for the coolant over the ECP probes, and a signal transmitter that transmits or carries ECP data to an external receiver. The ECP probes may be of any number and/or type, so as to detect ECP for different component materials, including stainless steel, a zirconium alloys, etc. The ECP probes may further detect ECP due to ion concentration, pH, etc. The ECP data may be transmitted through wired or wireless signal transmitters. Example methods include installing and using example embodiment ECP probe assemblies in nuclear reactors and facilities.

The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed.

Disclosed is a system for producing electromagnetic radiation with enhancement from a drift tube containing a cylindrical Smith-Purcell structure. The system includes a magnetically insulated linear oscillator. The oscillator includes a cylindrical resonant cavity having a traveling wave electron gun and a cooperating anode. The drift tube is formed of a hollow cylindrical conductive element that is positioned within a resonant cavity of the oscillator. The drift tube includes an inner surface and a pair of ends. The drift tube may be adapted such that the interaction between an electron beam, from the electron gun, passes through the inner space of the drift tube, and the internal grating, so as to produce RF radiation by the Smith-Purcell Effect. Spacing, face angle and shape of the grating, and the energy of the electron beam are determinants of the frequency of the RF radiation.

Aspects of the invention relate to several methods to deposit and regenerate target materials in neutron generators and similar nuclear reaction devices. In situ deposition and regeneration of a target material reduces tube degradation of the nuclear reaction device and covers impurities on the surface of the target material at the target location. Further aspects of the invention include a method of designing a target to generate neutrons at a high efficiency rate and at a selected neutron energy from a neutron energy spectrum.

Disclosed embodiments include electromagnetic flow regulators for regulating flow of an electrically conductive fluid, systems for regulating flow of an electrically conductive fluid, methods of regulating flow of an electrically conductive fluid, nuclear fission reactors, systems for regulating flow of an electrically conductive reactor coolant, and methods of regulating flow of an electrically conductive reactor coolant in a nuclear fission reactor.

Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.

Apparatus and methods for determining the absence or presence of contraband in an object with a fast neutron source for irradiating the object; a detector for measuring γ-rays emitted by the irradiated object from energy state relaxation as a result of neutron capture, typically after the object has been irradiated.

Disclosed is a coolant with dispersed neutron poison micro-particles, used in a supercritical water-cooled reactor (SCWR) emergency core cooling system. Since the neutron poison micro-particles are uniformly dispersed in the coolant of the emergency core cooling system for a long period time, their fluidity is not lowered even though the polarity of water is changed in a supercritical state. Therefore, the neutron poison micro-particles absorb neutrons produced from nuclear fission in a nuclear reactor core. Accordingly, the neutron poison micro-particles can be appropriately used as a means for controlling neutrons and stopping a nuclear reactor in the SCWR emergency core cooling system.

An improved grid for a nuclear reactor fuel assembly that has an egg-crate base grid as the primary support structure with each support cell of the base grid that supports a fuel rod having a lock-support sleeve that is rotatable within the support cell between a first and second orientation. In the first orientation the lock-support sleeve fits loosely within the support cell of the base grid and respectively, loosely receives the fuel rods that are loaded therein. The lock-support sleeves are then rotated to a second orientation that locks the fuel rods axially within the support cells.

A plug for heat-conducting tubes is equipped with: a plug main body, which is formed so as to be capable of being inserted into the heat-conducting tubes; a columnar member, which is capable of being inserted into and removed from the plug main body from the cylindrical open end of the plug main body, and has at its outer circumference a tapered surface; and a wedge member, which is formed so as to be capable of being inserted into and removed from the plug main body from the cylindrical open end of the plug main body, and has at its inner circumference a tapered surface which opposes the tapered surface of the columnar member when the wedge member is inserted into the plug main body.

Nonconjugated conductive polymers absorb radioactive iodine, therefore are useful for protection against nuclear radiation. These polymers have at least one double bond per repeat unit. The ratio of the number of double bonds to the total number of bonds along the polymer chain is less than half. Examples of nonconjugated conductive polymers include: cis-1,4-polyisoprene (natural rubber), trans-1,4-polyisoprene (gutta percha), polybutadiene, polydimethyl butadiene, poly(b-pinene), styrene butadiene rubber (SBR), polyalloocimene, polynorbornene and many others. Through interaction with iodine atoms the double bonds in the nonconjugated polymers transform into radical cations leading to a dark color. The iodine atoms remain (immobile) bound to the polymer chain through the charge-transfer interaction, these polymers are very inexpensive and can be easily processed into any shape, structure and size. Therefore, these are useful for protection against nuclear radiation including radioactive iodine. These polymers when used as a thick cover can provide safe storage of nuclear waste materials including spent fuel rods.

A compressor assembly and the method of using the same which includes an elongated spiral passageway within which a compact toroid plasma, such as a compact toroid plasma structure, can be efficiently compressed to a high-energy state by compressing the compact toroid plasma structure by its own momentum against the wall of the spiral passageway in a manner to induce heating by conservation of energy. The compressor assembly also includes a burn chamber that is in communication with the spiral passageway and into which the compressed compact toroid plasma structure is introduced following its compression.

A method and apparatus for the calibration of neutron flux monitoring devices used in a nuclear reactor core. The apparatus includes a transverse in-core probe (TIP) cable with a neutron absorber located a fixed distance apart from a TIP detector. The neutron absorber may be passed within close proximity of the neutron flux monitoring device such that a perceived drop in measured neutron flux occurs, whereupon the cable may be repositioned relative to the monitoring device to ensure that the TIP detector is within close proximity of the monitoring device for purposes of calibrating the monitoring device.

A method of fabricating a nuclear fuel comprising a fissile material, one or more hollow microballoons, a phenolic resin, and metal matrix. The fissile material, phenolic resin and the one or more hollow microballoons are combined. The combined fissile material, phenolic resin and the hollow microballoons are heated sufficiently to form at least some fissile material carbides creating a nuclear fuel particle. The resulting nuclear fuel particle comprises one or more fission product collection spaces. In a preferred embodiment, the fissile material, phenolic resin and the one or more hollow microballoons are combined by forming the fissile material into microspheres. The fissile material microspheres are then overcoated with the phenolic resin and microballoon. In another preferred embodiment, the fissile material, phenolic resin and the one or more hollow microballoons are combined by overcoating the microballoon with the fissile material, and phenolic resin.

An emergency core cooling system is provided with a hybrid safety system composed of an active safety system and a static safety system for ensuring the safety against a severe natural phenomenon such as a giant earthquake and a mega hurricane. An emergency core cooling system for a boiling water reactor includes four safety divisions in total: three safety divisions for an active safety system having a high pressure reactor core cooling system, a low pressure reactor core cooling system, a residual heat removal system, and an emergency diesel generator; and one safety division for a static safety system having an isolation condenser, a gravity drop reactor core cooling system, and a static containment vessel cooling system.

The invention relates to a nuclear fuel cladding totally or partially made of a composite material with a ceramic matrix containing silicon carbide (SiC) fibers as a matrix reinforcement and an interphase layer provided between the matrix and the fibers, the matrix including silicon carbide as well as at least one of the following additional carbides: titanium carbide (TiC), zirconium carbide (Zrc), and ternary titanium silicon carbide (Ti3SiC2). When irradiated and at temperatures of between 800° C. and 1200° C., said cladding can mechanically maintain the nuclear fuel within the cladding while enabling optimal thermal-energy transfer towards the coolant. The invention also relates to a method for making the nuclear fuel cladding.

Disclosed is a system for extracting energy from inertial confinement fusion reactions, which includes a central target chamber for receiving fusion target material. A plurality of energy drivers are arranged around the target chamber so as to supply energy to fusion target material in the chamber to initiate an inertial confinement fusion reaction of the material, releasing energy in the forms of fusion plasma and heat. A plurality of structures for extracting energy from the fusion reaction are provided, and comprise devices to extract high voltage DC energy from the fusion plasma, and means to extract thermal energy from the central target chamber. Power to the energy drivers may be supplied from high voltage DC energy extracted from the fusion reactions. The energy drivers may use an apodizing filter to impart a desired shape to the wavefront of the driving energy for causing the fusion reactions, to avoid hydrodynamic instabilities.

A sintered fuel pellet for a water nuclear reactor fuel rod including a peripheral wall extending along a central axis and two end faces. At least one of the end faces includes at least a first chamfer extending from the peripheral wall towards the central axis with a first non-zero slope with respect to a plane perpendicular to the central axis and a second chamfer extending from the first chamfer towards the central axis with a second non-zero slope with respect to a plane perpendicular to the central axis, wherein the first slope is different from the second slope.

A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG.

In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.

A portable target comprising: (a) a complaint, energy-absorbing backer; (b) a target on a surface of said backer; and (c) a support mechanism for holding said surface of said backer in a vertical position.

A ball ejection system for a roulette game is provided. The system includes a roulette wheel including a plurality of slots, at least one sensor, at least one ejector element, and a first driving mechanism. Each slot is defined by side walls and a bottom surface. Each bottom surface further includes an opening. The at least one sensor is position within each of the plurality of slots and are configured to emit a signal when detecting a ball within the slot. The ejector element is positioned below the roulette and includes at least one air blower. The air blower is configured to blow air circumferentially around the roulette wheel due to the detection of a ball on one of the sensors. Finally, the first driving mechanism is in communication with the at least one ejector element and configured to cause the initiation of the at least one air blower.

A card disposal system for a table game is provided that is capable of assuring the disposal of all of cards corresponding to a predetermined number of decks that are used at a game table without any deficiency and without any fraudulent diversion being made over such cards. A card disposal system for a table game of the present invention includes a discharge opening (4) for disposal of cards (3) after a game, a disposed card receiving board (5) for receiving the cards 3 from the discharge opening (4), a disposed card information acquiring means (6) that acquires information on the number (rank) of the card 3 placed in the discharge opening (4), a group information acquiring means (7) that acquires group information of the card (3) disposed of, a card counter (8) serving as a number counting means that counts the number of cards (3) that are placed in the discharge opening (4) for disposal, a deck examination means (13) that determines whether cards (3h) to be disposed of includes all the cards within a predetermined number of decks, for example, 416 cards in case of 8 decks (52 cards×8 decks), and an output means (10) that outputs a result of the determination. With the card disposal system, a void hole is made on the card to be disposed of, and the disposal of all the cards without any deficiency and without any fraudulent diversion being made over such cards is assured.

A reel backlight structure for a mechanical reel-type game includes an undifferentiated array of LED backlights. The rows of LEDs are closely spaced apart and may extend over an arc that encompasses both three vertical stop positions and four vertical stop positions. The LEDs are mounted on a flexible substrate that may be bent to match the radius of a reel strip and held in the desired radius with mounting attachment points.

The present invention generally relates to drinking games and apparatuses for the use therewith. Specifically, this invention relates to an improved drinking game component and cup alignment apparatus for use with various drinking games. The drinking game cup or attachment and cup alignment apparatus may be designed in such a manner as to allow for simplified, accurate and reliable positioning of one or more drinking cups on a playing surface.

Shooters must presently take their firearms out of their hands to then manually actuate a new target into shooting position. This Target Apparatus will allow the shooter to shine his laser light, infrared light, flashlight, or multi-spectrum light onto a Target Apparatus-mounted sensor that engages a drive means mounted upon the target frame that then forwards a new target into position without removing the firearm from its' shooting position. The unit also uses a unique target backing material that does not require targets to be made of rolls of coated or heavy material stock. The system can utilize rolls of cash register paper, cut sections of gift wrapping paper, hand towel rolls, or even paper towels as target materials without snagging and preventing the next target from being presented.

A grooved supporting member for assisting in the construction of a card structure is provided. Specifically, the grooved supporting member provides support for the beginning foundational planar stackable members. The grooved supporting member includes a planar base member, top surface, bottom surface, at least one edge, and at least one groove. Preferably, the groove is cut completely through the planar base member and provides lateral support for a planar stackable member. In the preferred embodiment, the grooved supporting member has four edges and four grooves, thus providing support for four planar stackable members to create the cell of a card structure. The user may employ one or more of the grooved supporting members of the present invention in a card structure. Further disclosed is a kit including a grooved supporting member of the present invention and a plurality of stackable planar members.

Each play of a base game increases the likelihood of winning a bonus award. A display provides a graphical indication of the change in likelihood of winning the bonus award. In one aspect, the bonus award comprises the opportunity to play a secondary game.

The present invention discloses a device, comprising a collapsible sports goal that is housed and anchored by a backpack.

A portable fabric target for ball sports has at least: a) three fabric panels, comprising a top first panel, a middle second panel; and a bottom third panel;b) the top first panel having i) a first bottom edge attached to at top edge of the second middle panel and ii) a second outside top edge;c) the top first panel having a support element extending away from the second outside top edge;d) the support element having a self-latching system that connects the second outside top edge to itself to form a loop or to a section of the top first panel to form a loop;e) the support element when locked around a pole supporting all weight of the portable fabric target without unlocking; andf) the bottom third panel having a stabilizing component thereon.