A latch plate for a lock device is proposed which comprises a latch plate proper and a film that covers the latch plate proper. The latch plate proper includes upper and lower finger portions between which a striker catching recess is defined. An upper surface of the lower finger portion includes a depressed main portion located near the bottom of the striker catching recess, a raised leading end portion and a stepped portion provided between the depressed main portion and the raised leading end portion. The film covers the latch plate proper except the raised leading end portion. The film covers the depressed main portion of the upper surface in such a manner that an outer surface of the film is flush with the stepped portion. When the film is depressed by the striker, the stepped portion enhances a function is to stop a movement of the striker toward a mouth of the striker catching recess.

The present disclosure describes a method of manufacture and a structure for an automobile seat cover that includes a seat cover body with an outer perimeter, a seat cover skirt with a first edge sewn with an overlock stitch to the seat cover body for a majority of the outer perimeter, and a second edge, distal from the first edge, comprising a tie element extending for a majority of the second edge around a seat opening in the seat cover. A portion of the seat cover skirt and the seat cover body corresponding to a location of at least one airbag installed in an automobile seat cover over which the seat cover is to be placed are sewn together with one of a straight stitch and a lock stitch instead of the overlock stitch. In some implementations, the thread used is a brightly colored string.

Embodiments of the present invention include a vehicle seat having a frame member and a reinforcing member for reinforcing the frame member. The frame member has an elongated portion. The elongated portion is formed of resin and preferably has a flat-plate-like or bar-like configuration. The elongated portion includes a first portion, a front second portion and a rear second portion. The first portion may be arranged in a longitudinal manner with respect to the vehicle seat and extends vertically. The front second portion extends in the lateral direction of the vehicle seat from a front end of the first portion. The rear second portion extends in the lateral direction of the vehicle seat from a rear end of the first portion. The elongated portion is configured so that a neutral axis is positioned between the front and rear second portions.

A seat back frame includes: a first side member and a second side member each formed into an elongated shape along an up-and-down direction of a seat back so as to support each side portion of the seat back; and a belt guide portion on which tension of a seat belt is applied when the seat belt is pulled, the belt guide portion being formed in an upper portion of the first side member and guiding the seat belt having the one end retained by a seat belt retaining member. The first side member is formed of a sheet of steel plate and includes: a side member side wall portion formed in parallel to a direction of application of the tension of the seat belt on the belt guide portion and formed continuously along a longitudinal direction of the first side member; a side member front wall portion formed on a front side of the vehicle with respect to the side member side wall portion; and a side member rear wall portion formed on a rear side of the vehicle with respect to the side member side wall portion, the first side member having an open cross-sectional shape.

A vehicle seat includes a seat cushion, a seat back connected to the seat cushion and including a storage portion, a belt member configured to restrain an occupant while the belt member is routed from a side of the seat back to a side of the seat cushion, and a rerouter member configured to be taken out from the storage portion of the seat back and connected to the belt member to change a routing position of the belt member at a middle portion thereof. In a state where a portion of the rerouter member is stored in the storage portion, another portion of the rerouter member is exposed from the storage portion.

A vehicle seat comprises: left and right side frames (4) which constitute left and right portions of a seat back frame (2); a reinforcing frame (pipe frame 5) disposed adjacent to one side frame (4) in a lateral direction, and configured to reinforce the side frame (4); and a force-receiving member (bracket 7) disposed adjacent to the one side frame (4), provided discretely from the reinforcing frame, and configured to receive a load from another member. The force-receiving member is disposed opposite to the reinforcing frame with the side frame 4 disposed therebetween, and directly fixed to the reinforcing frame.

An embodiment of the present invention provides an apparatus, comprising at least one anti-parallel pair VVC network comprised of two parallel VVCs with one biased in the opposite polarity of the other and at least one anti-series VVC network comprised of two VVCs configured in series, one biased in the opposite polarity of the other such that the resulting AC capacitive variations produce a desired capacitance variation.

A communication module is provided in which its characteristic of separation between its first and second tuner units is improved. The module is equipped with a circuit board having a first main surface, and a second main surface opposite to the first main surface; a first amplifier arranged on the first main surface, for amplifying a first signal; a first mixer arranged on the first main surface, for converting a signal supplied from the first amplifier to an intermediate-frequency signal; a second amplifier for amplifying a second signal; and a mixer for converting a signal supplied from the second amplifier to an intermediate-frequency signal, both arranged on the second main surface of the circuit board.

Methods and apparatus for computing the carrier frequency of a transmitter using frequency modulated digital data to compensate for frequency shifting of the transmitter and the receiver local oscillators and for bandwidth adjustment of the receiver's filter. In particular, methods and apparatus are disclosed for binary systems transmitting “1” and “0” data using decoded or undecoded received signals.

An optical beam scanning apparatus is disclosed, including: a laser source that emits an optical beam, a deflection part that deflects the optical beam, a light receiving part that receives a returning light of the optical beam which is deflected toward the laser source by the deflection part, a signal generation part that generates a synchronization detection signal, and an optical source drive part that conducts a lighting control of the laser source. The light receiving part is arranged in vicinity to the laser source. The signal generation part detects a timing at which the light receiving part receives the returning light, by an output signal from the light receiving part to generate the synchronization detection signal. The optical source drive part conducts the lighting control of the laser source in response to the synchronization detection signal as a reference.

In one aspect, the present invention is directed to an earthquake detection and alarming apparatus, comprising: a transparent object (46) having a concave surface on the top thereof; a rollable object (34) placed on the concave surface; an apiary of light projectors (30) placed above the concave surface; an apiary of light receivers (38) correspondingly to the apiary of light projectors, the apiary of light receivers being placed below the concave surface; and circuitry for determining: (a) vibrating frequency and amplitude of the rollable object with reference to the concave surface from sensing of the receivers (38); and (b) deducing therefrom the arrival of primary waves.

A printing system that has a printhead assembly for printing media fed along a media path and a plurality of service modules for the printhead assembly. Each of the service modules is configured to operate in a plurality of different modes and each of the service modules are independently operable.

An apparatus includes a head transducer configured to interact with a magnetic recording medium and a heater configured to thermally actuate the head transducer. A thermal sensor at or near the head transducer is configured to produce a sensor signal. Circuitry is coupled to the heater and configured to cause an oscillation in heater power. The heater power oscillation causes an oscillation in the sensor signal. A detector is coupled to the thermal sensor and configured to detect head-medium contact using the oscillating sensor signal and heater power.

A container data center includes a container, a plurality of power supplies, an electric switch system, a plurality of normally closed switches, an alarm device, and a controller. The electric switch system is received in the container. The plurality of normally closed switches are connected between the power supplies and the electric switch system. Each normally closed switch is connected with a corresponding one of the power supplies in series. The controller is connected to the normally closed switches and the alarm device, configured for receiving earthquake information containing an earthquake intensity, and configured for controlling the alarm device to activate alarms and controlling some of the normally closed switches or all the normally closed switches to open when the earthquake intensity is equal to or greater than a predetermined earthquake intensity.

An inner peripheral surface of a tube-shaped inner casing has a regular hexagonal shape when viewed from the axial direction, a plurality of pins are arranged in the inner casing so as to take a posture parallel to the axial direction of the inner casing, and in this arrangement, a plurality of rows of the pins arranged in a predetermined direction are arranged in a direction perpendicular to the row direction of the pins, the adjacent pins of the adjacent rows are offset from each other in the row direction of the pins, and each pin contacts the pins adjacent thereto.

A forging heat resistant steel of an embodiment contains in percent by mass C: 0.05-0.2, Si: 0.01-0.1, Mn: 0.01-0.15, Ni: 0.05-1, Cr: 8 or more and less than 10, Mo: 0.05-1, V: 0.05-0.3, Co: 1-5, W: 1-2.2, N: 0.01 or more and less than 0.015, Nb: 0.01-0.15, B: 0.003-0.03, and a remainder comprising Fe and unavoidable impurities.

Disclosed are: a casting aluminum alloy that is excellent in elongation as alternative properties of a high cycle fatigue strength and a thermal fatigue strength and is suitably usable for a casting for which both of the excellent high cycle fatigue strength and the excellent thermal fatigue strength are required, for example, an internal combustion engine cylinder head; a casting made of the aluminum alloy; a manufacturing method of the casting; and further, an internal combustion engine cylinder head composed of the aluminum alloy casting and manufactured by the manufacturing method of the casting. The casting aluminum alloy contains, in terms of mass ratios, 4.0 to 7.0% of Si, 0.5 to 2.0% of Cu, 0.25 to 0.5% of Mg, no more than 0.5% of Fe, no more than 0.5% of Mn, and at least one component selected from the group consisting of Na, Ca and Sr, each mass ratio of which is 0.002 to 0.02%.

There is provided a bearing for motor-powered fuel injection pumps, made from Cu—Ni-based sintered alloy, which is able to be obtained at a low cost, having excellent corrosion and abrasion resistances. The bearing contains 10 to 20% by mass of Ni, 5 to 13% by mass of Sn, 0.1 to 0.8% by mass of P, 1 to 6% by mass of C, and a remainder containing Cu and inevitable impurities, and is formed with a Ni—Sn—Cu—P phase containing at least 30% by mass of Sn in a grain boundary, and has a 8 to 18% porosity. The Ni—Sn—Cu—P phase contains 30 to 49% by mass of Ni, 10 to 30% by mass of Cu, 0.5 to 1.5% by mass of P, and a remainder containing Sn and inevitable impurities.

Magnesium alloys containing: Y: 2.0-6.0% by weight Nd: 0-4.0% by weight Gd: 0-5.5% by weight Dy: 0-5.5% by weight Er: 0-5.5% by weight Zr: 0.05-1.0% by weight Zn+Mn:

A multipurpose tool and method usable to remove debris and/or other retentate from a skimmer basket or a filter associated with a swimming pool, and/or to remove the skimmer well lid and the skimmer basket and/or filter from a skimmer well. The tool comprises two elongate members pivotally connected, each elongate member having a protrusion connected thereto at one end and a handle at the other. Each elongate member can have a scooping element connected thereto. The protrusions can point away from each other and can be adapted to move away from each other in response to the handles being moved towards each other.

A cleaning assembly including a disposable cleaning implement having a cleaning element mounted to a fitment having an elongated post. The cleaning assembly includes an elongated maneuvering wand having a handle portion and a distal implement attachment end thereof. A gripping mechanism is coupled to the wand attachment end, and is configured to releasably grip the fitment post to mount the cleaning implement. The gripping mechanism and the maneuvering wand cooperate to substantially limited pivotal movement of a longitudinal axis of the fitment post, relative a longitudinal axis of the gripping mechanism to not more than about 0 degrees to about 25 degrees when the fitment post is subjected to forces radial to the longitudinal axis of the fitment post. In another aspect, the frictional drag between the sliding components is significantly reduced, enabling a tool assembly with a high axial holding force for the cleaning implement, but with a significantly lower, consumer friendly release force for the Implement during release operation of the tool assembly.

A tool to grasp objects, and to expand and/or retract while holding the objects, wherein the tool can include at least one handle disposed on a first end of an expandable assembly. At least one handle can be adapted to expand the expandable assembly when actuated or when there are a pair of handles and they are moved towards one another and retract the expandable assembly when they are moved away from one another. A gear assembly can be disposed on a second end of the expandable assembly. The tool can allow users to reach, grasp, move, and release remote objects.

A pick-and-place vacuum nozzle including a a nozzle body, a vacuum chamber within the nozzle body, a cavity formed in a lower surface of the nozzle body below the vacuum chamber, wherein the cavity is shaped to hold a head gimbal assembly, a back pressure relief hole passing through the nozzle body and connected to the vacuum chamber, the back pressure relief hole communicating with an exterior of the nozzle body, wherein a diameter of the back pressure relief hole is between 0.5 mm and 1 mm. The backpressure relief hole prevents light parts from sticking to the nozzle tip after vacuum is no longer applied.

A trash spearing tool and method are provided. The tool includes a spearing pin, a trigger assembly, an inner tube, and an outer tube. The trigger assembly is movable between a normal position and an activated position. The outer tube is slidable between a storage position and a use position. The spearing pin is operatively coupled to the trigger assembly in such manner that, when the outer tube is in the use position and the trigger assembly is in the normal position, the spearing pin is normally biased to an extended position in which a portion of the spearing pin extends from the outer tube and, when the outer tube is in the storage position and the trigger assembly is in either the normal position or use position, the spearing pin to in a retracted position in which the spearing pin does not extend from the outer tube.

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.

A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided.

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.

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 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.

UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.

A jet pump beam (hereinafter, referred to as a beam) is fitted into a pair of projecting portions installed to a transition piece, and after the beam is arched, a beam bolt engaged with the beam is tightened. An end of the beam bolt comes in contact with a top surface of an insert member fitted into an elbow disposed between the pair of projecting portions. An ultrasonic sensor head is fixed to the beam bolt, and ultrasonic waves are sent to the beam bolt from the ultrasonic sensor in the ultrasonic sensor head. An ultrasonic measuring apparatus obtains echo intensity of each of reflected waves generated at the end of the beam bolt and a bottom surface of the insert member, and based on the echo intensities, an echo intensity ratio R is calculated. The installed state of the beam is checked using the echo intensity ratio R.

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.

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.

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.

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.

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.

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 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.

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 detection device is used in a gaming machine that detects numbers of dots on a plurality of dice having wireless tags. The detection device reads the wireless tags which are embedded on each face of the dice by a reader having an antenna. The antenna of the reader includes a first antenna portion disposed substantially in a central portion of a field that supports the dice, and formed in a substantially circular shape, and a plurality of second antenna portions disposed so as to superimpose a detection area of the first antenna portion, and having a detection area larger than the first antenna portion. The first antenna portion and the plurality of the second antenna portions are disposed so as to have a portion of detection areas mutually superimposed on a playing board.

Gaming systems and methods provide a tournament game which selectively awards an enhanced tournament play result. The enhanced tournament play result may be of variable value which is selected for the given instance in order to place the receiving tournament player in some predetermined rank in the tournament. Such a variable enhanced tournament play result in the tournament game may be used to help keep all participants interested in the tournament, even those participants who trail the tournament leaders by a wide margin.