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.

A sheathed, annular metal fuel system is described. A metal fuel pin system is described that includes an annular metal nuclear fuel alloy. A sheath may surround the metal nuclear fuel alloy, and a cladding may surround the sheath. A gas plenum may also be present. Mold arrangements and methods of fabrication of the sheathed, annular metal fuel are also described.

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.

A nuclear fuel assembly tie plate is provided. The nuclear fuel assembly tie plate is formed by intersecting strips delimiting between them tubular guide cells each for allowing a fuel rod to extend through the tie plate. The strips delimit between them tubular flow cells separate from the guide cells, each flow cell for allowing coolant flow through the tie plate. Guide cells and flow cells are arranged at nodes of a lattice defined by a repeating pattern comprising four corner nodes in a square lattice arrangement and a central node at the center of the four corner nodes, with one guide cell at each corner nodes, separated by a pair of parallel spaced strips intersecting a pair of parallel spaced strips, the two pairs of strips delimiting a four-walled central flow cell at the center node.

This document's object is to provide an axial power distribution control method in which only the control of an axial power distribution in a nuclear reactor with a simple operation with a clear operational target keeps the control of a xenon oscillation, thereby suppressing the xenon oscillation to an extremely small magnitude in advance at the same time. An axial power distribution control method comprises an axial offset calculation step of calculating an axial offset of the current power distribution (AOP) and axial offsets of the power distributions (AOX, AOI) which would give the current xenon and iodine distributions under equilibrium conditions, respectively, based on relative powers (PT, PB) in the upper and lower halves of the nuclear reactor core, a parameter calculation step of calculating parameters (DAOPX, DAOIX), a trajectory display step of displaying a trajectory to plot the parameters (DAOPX, DAOIX) on one and the other axis, respectively, an allowable range excess judgment step of judging if the axial offset of the current power distribution (AOP) exceeds an allowable range, an alarming step of giving the alarm when the AOP exceeds the allowable range, and a control rod moving step of controlling the movement of control rods to guide the plot to the major axis of an ellipse formed by the trajectory of said parameters upon receipt of the alarm.

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.

A cask cushioning body includes an end-surface side member (2) in which a plurality of plates (21, 22) made of steel are formed at a distance between plate surfaces of the plates (21, 22) that face each other, and in which the plate surfaces of the plates (21, 22) are arranged along an end surface (100a) of a cask (100), and a circumferential-surface side member (3) that forms a cylindrical body (31) made of steel, one end of which is connected to a periphery of the end-surface side member (2), and that is arranged along an end-portion outer-circumferential surface (100b), wherein an impact absorber (4) that absorbs an impact by deforming is provided outside of the end-surface side member (2) and the circumferential-surface side member (3).

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 for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons. A method for producing antiprotonic x-ray cascade spectra.

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 CRDS unlatching tool includes a support assembly and a latching assembly, wherein the support assembly is received within the latching assembly in a manner wherein the latching assembly is moveable relative to the support assembly. The support assembly has a plurality of latch fingers and at least one pin, each of the latch fingers being movable between a latched position wherein the latch finger is structured to engage and hold the CRDS an unlatched position wherein the latch finger is structured to not engage the CRDS. The latching assembly includes a first sleeve member and a second sleeve member, the second sleeve member having at least one slot, wherein the at least one pin is moveably received within the at least one slot. The latching assembly is movable from a latched state to an unlatched state wherein the latch fingers are actuated by the first sleeve member.

There is provided a holding device which can hold a molten corium for a predetermined period even when the molten corium is exposed to heat or undergoes any chemical reaction and which is applicable to practical use. There is provided a holding device provided below a nuclear reactor pressure vessel for holding a molten corium, wherein the holding device includes a base material in contact with a cooling medium, and a multilayer stack structure on the base material. The multilayer stack structure has a first layer having heat-resistant property, a second layer formed on the first layer and having heat-resistant property with lower heat conductivity than that of the first layer, and a third layer formed on the second layer and having corrosion-resistant property and impact-absorbing property.

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.

The invention refers to a fuel assembly comprising a lower end structure, an upper end structure including a top nozzle (5), a plurality of fuel rods and a plurality of guide thimbles (3). The top nozzle includes a passageway and an annular groove (10) in said passageway. A sleeve (11) is provided for attaching the guide thimble (3) to the top nozzle (5). The sleeve has at least three slots (12) and includes at least three bulges (13). Each bulge (13) has two ends and extends between two of the slots (12). At least one of the ends of the bulge (13) extends to a position at a distance (d) from the respective slot (12). The invention also refers to a guide thimble device (9) for use in a fuel assembly.

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 connector-equipped communication module includes a communication module and a connector. The communication module includes a wiring board including antenna-mounted and IC-mounted regions at different positions in a planar view, an antenna element mounted in the antenna-mounted region, a wireless IC and a mounted component mounted in the IC-mounted region, and side terminals in the IC-mounted region and peripheral portions near the IC-mounted region. The connector includes a receiving portion including a placement portion configured to mount the communication module and a wall portion extending around the placement portion, inner wall terminals on an inner side of the wall portion at positions facing the side terminals, and external terminals located outward of the receiving portion and electrically connected to the inner wall terminals. In a state where the communication module is received in the receiving portion, the inner wall and side terminals are fitted so as to contact with each other.

A designer-adaptive visual code (32, 32', 32″) includes a user-selected set glyphs (36, 36', 36″, 36'−), a user-selected set of allowable glyph orientations relative to a user-selected reference angle, and a user-selected spatial arrangement of the glyphs (36, 36', 36″, 36'″). The user-selected set of glyphs (36, 36', 36″, 36'″) has a size sufficient to recover geometric characteristics of at least one repeating code portion so as to generate an analyzable image when captured via a camera-equipped mobile device (26). The user-selected spatial arrangement of the glyphs (36, 36', 36″, 36'″) includes the at least one repeating code portion (34) to be visible on a surface from at least two different areas of the surface.

A tag includes an integrated circuit thereon, including memory, antenna means for RF transmission of data acquired by the integrated circuit, a sensor sensing environmental conditions to which the sensor is subjected, the sensor providing signals based on the environmental conditions to the integrated circuit, a thermistor device of increasing the accuracy of the tag by confining on-board calculation data to a resistance domain and leaving conversion of the data to a temperature domain for an external device once the data is retrieved from the tag's memory.

A graphic may include a consumable and having optically encoded information.

A method for scanning and decoding encoded symbols comprises processing low resolution image data from a full field of view and/or high resolution image data from one or more windowed segments of the field of view to provide imaging that is easily adaptable to different types of symbols and varying environmental conditions. The scanning method can be switched between the low resolution mode and the high resolution mode automatically based on whether the low resolution data is sufficiently accurate to decode the symbol.

An RFID event tracking and management system provides a standardized approach that can be utilized by various industry verticals. Loss of captured event data, such as RFID generated through an RFID event, can be prevented through a series of guarantee semantics. Approaches also provide for role-based data visibility. Queries received from a user or entity can be dynamically modified based on the role of the user/entity using a virtual private database (VPD). The modified query can result in a virtual private database automatically hiding or restricting access to event data at row, column, and/or cell levels, so that an authorized user/entity is only able to access data to which that user/entity should have access.

Systems, methods, and devices for providing and managing electronic event tickets are provided. For example, a device for managing an electronic event ticket may include a processor configured to run an electronic ticket management application, a memory device configured to store data associated with the electronic ticket management application, an electronic display configured to display at least a portion of the data associated with the electronic ticket management application, and an input/output interface configured to receive an electronic ticket and the data associated with the electronic ticket for management by the electronic ticket management application. The electronic ticket management application may be configured to enable the electronic device to gain entry to an event and to obtain at least one other event-related benefit after the electronic ticket is received by the input/output interface.

Apparatuses, methods, and systems pertaining to the verification of portable consumer devices are disclosed. In one implementation, a verification token is coupled to a computer by a USB connection so as to use the computer's networking facilities. The verification token reads identification information from a user's portable consumer device (e.g., credit card) and sends the information to a validation entry over a communications network using the computer's networking facilities. The validation entity applies one or more validation tests to the information that it receives from the verification token. If a selected number of tests are passed, the validation entity sends a device verification value to the verification token, and optionally to a payment processing network. The verification token may enter the device verification value into a CVV field of a web page appearing on the computer's display, or may display the value to the user using the computer's display.

System, including a code scanner, for using multi-function codes, such as multi-function QR codes, MobiTags, ShotCodes, 2-dimensional bar codes, 3-dimensional bar codes, or images to open multiple ports of a telephone device. One of the ports is a text port, enabling the system to obtain the telephone number of a device that reads a code associated with an item and then generate a lead for follow-up by an agent. The lead is sent to the agent via a text or email message. The system may also pass the lead to other agents if the first agent doesn't respond, and it may also send additional information to the telephone device. The system may include a database of item-associated information and the capability of accessing the item-associated information for inclusion in outgoing messages to the agents and/or the telephone device.

Credit applicants may apply for instant credit, and use an instant account number (“IAN”) to make purchases after the instant credit has been granted. Fraud control methods may be used in authorizing the instant credit. When the IAN is issued to purchase airline tickets, it can be ensured that the applicant's last name matches the passenger's last name for the airline ticket being purchased, and that the ticket will not be renamed or sold. When the IAN is issued in conjunction with a partner's loyalty or rewards program, the applicant's account information with the rewards program is captured. It is ensured that the applicant has some tenure with the partner and that data submitted by the applicant is consistent with data on file with the partner.

According to one embodiment, a system includes a processor and an interface. The interface receives, from a terminal, planned-deposit information. The terminal is at a location that is remote from a deposit location. The processor associates a deposit identifier with the planned-deposit information and stores the planned-deposit information and the deposit identifier in a memory. According to one embodiment, a method includes recognizing, at a deposit location, a deposit identifier. The method includes identifying, based on the deposit identifier and information stored in a memory, a planned deposit. The method includes detecting that the planned deposit has been delivered to a depository and determining, by a processor and based on one or more business rules, an availability of funds associated with the planned deposit.

A transaction is preprocessed wirelessly in response to a wireless transaction preprocessing user device being in a queue for a point-of-transaction. The transaction that was preprocessed is then completed in response to the wireless transaction preprocessing user device reaching the point-of-transaction. Financial transactions and/or purchase of goods and/or services may thereby be preprocessed wirelessly and then completed at a point-of-transaction. Related devices and computer program products are also disclosed.

A banking system operates responsive to data read from data bearing records. The system includes an automated banking machine comprising a card reader. The card reader includes a movable read head that can read card data along a magnetic stripe of a card that was inserted long-edge first. The card reader includes a card entry gate. The gate is opened for a card that is determined to be properly oriented for data reading. The card reader can encrypt card data, including account data. The card data is usable by the machine to authorize a user to carry out a financial transfer involving the account.

A banking system is controlled responsive to data read from data bearing records. The banking system includes an automated banking machine. The machine is operable to carry out a financial transaction for a person responsive to a determination that the person is an authorized user of the machine based on correspondence between identifying data read by a reader of the machine and data store information. The machine includes a check acceptor that is operative to receive checks from authorized machine users. The check acceptor is operable to continuously move a received check along its transport path while simultaneously rotationally orienting the check into alignment with the transport path. A check determined not to have at least one property of an acceptable check is returned to the machine user. Acceptable checks are processed and stored in the machine.

An approach for associating a card (e.g., a transaction card, an identification card, etc.) that corresponds to a primary account with one or more ancillary accounts (e.g., a library account, etc.) includes obtaining information from the card and associating that information with an ancillary account. The card may then be used to access the ancillary account. The card may be a transaction card and the primary account may be a financial account. The ancillary account may be a library account. When the card is a transaction card, fees associated with the ancillary account may be charged to the financial account.

A mobile device utilizes an embedded near field communication (NFC) capability to interact with a contactless transaction card to automatically obtain information from the card, e.g. reducing or eliminating the burden of manual user entry of the account information or the like into the mobile device. The mobile device, for a financial account transaction example, may read the information from the card at the time of a transaction, e.g. to facilitate an on-line purchase, an in-store purchase, ATM transaction or the like. The mobile device may store the information from one or more contactless transaction cards, for use in future transactions of various types. The mobile device and/or a server in communication with the mobile device may track various user activities on the mobile device that also utilize information obtained from the contactless transaction card.

Communication between a retailer and a customer is disclosed. A payment card and a communication identifier addressing a wireless transceiver of a mobile apparatus are registered to an electronic service. The mobile apparatus receives, with the wireless transceiver, a plurality of packets relating to payments with the payment card of a plurality of trades of various commodities between the user and a plurality of various retailers, from the electronic service, extracts from the received plurality of the packets transaction information relating to the payments and supplementary information, and communicates, with a user interface, the extracted transaction information and the supplementary information to the user.

A ticket reading system comprising a portable head section with an aperture and means for removably affixing the head section to a stationary fixture; in the head section, a camera with a field of view over the aperture to read visible code elements of a ticket; an RFID antenna and module adjacent to the aperture to read RFID/NFC code elements from a device or tag; a wireless network communication module to communicate data packets among a processor and a wireless network access point; means for ticket validation feedback; instructions which cause: receiving a ticket identifier value from the camera or RFID module; sending a request via the wireless network for a server computer to validate the ticket identifier value; receiving a ticket validation response from the server computer; based upon the response, driving the means for providing ticket validation feedback to generate either valid response feedback or invalid response feedback.