New 6xxx aluminum alloy bodies and methods of producing the same are disclosed. The new 6xxx aluminum alloy bodies may be produced by preparing the aluminum alloy body for post-solutionizing cold work, cold working by at least 25%, and then thermally treating. The new 6xxx aluminum alloy bodies may realize improved strength and other properties.

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%.

Methods for determining a recovery state of a metal alloy are disclosed herein. In one example, a fluctuation in a crystallographic grain orientation of the metal alloy is determined by utilizing electron backscatter diffraction (EBSD) data of the metal alloy. A processor of an electron backscatter diffraction machine utilizes a local orientation deviation quantifier to correlate the fluctuation in the crystallographic grain orientation of the metal alloy with a plastic strain recovery of the metal alloy. Other examples of the method are also disclosed herein.

Alloys and methods for preparing the same are provided. The alloys are represented by the general formula of (ZraAlbCucNid)100-e-fYeMf, wherein a, b, c, and d are atomic fractions, in which: 0.472≦a≦0.568; 0.09≦b≦0.11; 0.27≦c≦0.33; 0.072≦d≦0.088; the sum of a, b, c, and d equals 1; e and f are atomic numbers of elements Y and M respectively, in which 0≦e≦5 and 0.01≦f≦5; and M is selected from the group consisting of Nb, Ta, Sc, and combinations thereof.

The distribution of Ni—Si compound grains is controlled to thereby improve the properties of Corson alloys. The copper alloy for electronic materials comprises 0.4 to 6.0% mass of Ni and 0.1 to 1.4% by mass of Si, with the balance being Cu and unavoidable impurities. The copper alloy comprising: small particles of Ni—Si compound having a particle size of equal to or greater than 0.01 μm and smaller than 0.3 μm; andlarge particles of Ni—Si compound having a particle size of equal to of greater than 0.3 μm and smaller than 1.5 μm. The number density of the small particles is 1 to 2000 pieces/μm2 and the number density of the large particles is 0.05 to 2 pieces/μm2.

A platinum-free silver alloy may include about 0.1% to 0.9% Au, about 83% to 90% Ag, about 2% to 3% Pd, about 3% to 5% Zn, about 2% to 8% Cu, about 0.01% to 0.4% B, about 0.1% to 0.3% Ge, and about 0.01% to 0.03% Ir.

A device includes a chemical hydride fuel pellet having a plurality of holes extending from a first end to a second end. A plurality of tubes formed of water vapor permeable and hydrogen impermeable material extend from the first end to the second end through the tubes. A container has an inlet for water vapor containing gas coupled to the first end of the tubes and an outlet coupled to the second end of the tubes. A hydrogen outlet is coupled to the fuel pellet.

Provided are a bake hardening steel having a crystalline grain size of ASTM No. 9 or more and a method for preparing the bake hardening steel by controlling the winding, rolling and cooling conditions. The bake hardening steel includes: C:0.0016˜0.0025%, Si:0.02% or less, P:0.01˜0.05%, S:0.01% or less, sol.Al:0.08˜0.12%, N:0.0025% or less, Ti:0.003% or less, Nb:0.003˜0.011%, Mo:0.01˜0.1%, B:0.0005˜0.0015% or less, balance Fe and other inevitable impurities, wherein % is weight %, and Mn and P satisfy the relation of −30(° C.)≧803P−24.4Mn−58.

A nickel-chromium-cobalt-molybdenum alloy includes (in weight %) Cr 21-23%, Fe 0.05-1.5%, C 0.05-0.08%, Mn≦0.5%, Si≦0.25%, Co 11-13%, Cu≦0.15%, Mo 8.0-10.0%, Ti 0.3-0.5%, Al 0.8-1.3%, P

Magnesium-based hydrogen storage alloys with addition of transition and rare earth elements were produced by conventional induction melting and by rapid solidification. The magnesium based-alloys of this invention posses reversible hydrogen storage capacities ranging from 3 to over 6 wt. %, and excellent performance on the hydrogen absorption and desorption kinetics.

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 nickel-base superalloy is characterized by the following chemical composition (details in % by weight): 7.7-8.3 Cr, 5.0-5.25 Co, 2.0-2.1 Mo, 7.8-8.3 W, 5.8-6.1 Ta, 4.9-5.1 Al, 1.0-1.5 Ti, 1.0-2.0 Re, 0.11-0.15 Si, 0.1-0.7 Hf, 0-0.5 Nb, 0.02-0.17 C, 50-400 ppm B, remainder Ni and production-related impurities. The alloy is distinguished by a very high resistance to oxidation, resistance to corrosion and good creep properties at high temperatures.

A Cu—Ni—Mo alloy thin film, including Ni as a solution element and Mo as a diffusion barrier element. Ni and Mo are co-doped with Cu. The enthalpy of mixing between Mo and Cu is +19 kJ/mol, and the enthalpy of mixing between Mo and Ni is −7 kJ/mol. The atomic fraction of Mo/Ni is within the range of 0.06-0.20 or the weight faction of Mo/Ni within the range of 0.10-0.33. The total amount of Ni and Mo additions is within the range of 0.14-1.02 at. % or wt. %. A method for manufacturing the alloy thin film is also provided.

Basic zinc cyanurate fine particles are produced by subjecting a mixed slurry to wet dispersion using a dispersion medium at a temperature in the range of 5 to 55° C., the mixed slurry being formed by blending water, cyanuric acid, and at least one component selected from zinc oxide and basic zinc carbonate such that the cyanuric acid concentration is 0.1 to 10.0 mass % with respect to water.

An object of the present invention is to provide a Ni-based superalloy, especially for a conventional casting, having a good balance among high temperature strength, corrosion resistance and oxidation resistance, as compared to a conventional material. The Ni-based superalloy comprises Cr, Co, Al, Ti, Ta, W, Mo, Nb, C, B, and inevitable impurities, the balance being Ni, the Ni-based superalloy having a superalloy composition comprising, by mass, 13.1 to 16.0% Cr, 11.1 to 20.0% Co, 2.30 to 3.30% Al, 4.55 to 6.00% Ti, 2.50 to 3.50% Ta, 4.00 to 5.50% W, 0.10 to 1.20% Mo, 0.10 to 0.90% Nb, 0.05 to 0.20% C, and 0.005 to 0.02% B.

Disclosed are metal-containing precursors having the formula Compound (I) wherein: —M is a metal selected from Ni, Co, Mn, Pd; and —each of R-1, R2, R3, R4, R5, R6, R7, R8, R9, and R10 are independently selected from H; a C1-C4 linear, branched, or cyclic alkyl group; a C1-C4 linear, branched, or cyclic alkylsilyl group (mono, bis, or tris alkyl); a C1-C4 linear, branched, or cyclic alkylamino group; or a C1-C4 linear, branched, or cyclic fluoroalkyl group. Also disclosed are methods of synthesizing and using the disclosed metal-containing precursors to deposit metal-containing films on a substrate via a vapor deposition process.

Provided is one aspect of copper alloy sheet containing 4.5% by mass to 12.0% by mass of Zn, 0.40% by mass to 0.90% by mass of Sn, 0.01% by mass to 0.08% by mass of P, as well as 0.005% by mass to 0.08% by mass of Co and/or 0.03% by mass to 0.85% by mass of Ni, the remainder being Cu and unavoidable impurities. The copper alloy sheet satisfies a relationship of 11≦[Zn]+7×[Sn]+15×[P]+12×[Co]+4.5×[Ni]≦17. The one aspect of copper alloy sheet is produced by a production process including a finish cold rolling process at which a copper alloy material is cold-rolled. An average grain size of the copper alloy material is 2.0 μm to 8.0 μm, circular or elliptical precipitates are present in the copper alloy material, and an average particle size of the precipitates is 4.0 nm to 25.0 nm, or a percentage of precipitates having a particle size of 4.0 nm to 25.0 nm makes up 70% or more of the precipitates.

A gripper assembly for use with a moving device is disclosed. The moving device can be a mechanical device such as a robot. The gripper assembly includes a platform and an elongate arm extending from the platform. The elongate arm is in the form of least one elongate member. Each elongate member has a body which has a proximal end and an opposed distal end. A gripping mechanism is rotatably supported relative to the arm, and includes a holder having a pivoting arm pivotably joined to the body in the region of the distal end of the body. An actuator is in operable communication with the pivoting arm to impart pivotable movement to the pivoting arm and rotational movement to said gripping mechanism about a horizontal axis upon actuation of the actuator. The gripper assembly may have a center of mass substantially aligned with a vertical rotation axis of the gripper assembly.

An apparatus for safely retaining an eye implant lens for transport and access for inspection and use in which a holding apparatus has a chamber for holding a lens. In one embodiment the chamber has a pin on which a lens can be placed and a ramp leading to the pin so that a gripping member can slide up the ramp into proper placement to grip the lens and remove it. The gripper can be configured so that after removing the lens from the holding apparatus, it can be used to implant the lens. Also, a system including the apparatus and a bottle assembly that will hold the apparatus in the bottle. A method for holding an eye implant lens in which a lens is placed in the apparatus which can then be placed in a bottle assembly.

A combination support stand and carrying handle apparatus for use with an associated tablet device having a generally rectangular conformation with opposite front and back substantially planar surfaces. The apparatus includes a mounting member, a handle member, and a support stand for holding the associated tablet device on surfaces at selected angles for convenience of use of the tablet device. The carrying handle is grippable by the hand of an associated user. The support stand apparatus and carrying handle apparatus may be provided individually without the other.

A suction gripper for transferring ophthalmic lenses from a storage cup into a centering cup has a suction head with several suction openings and several suction cups, wherein the suction cups are positioned on a convexly rounded surface. At least some of the suction openings are arranged in the suction cups and at least one suction opening is arranged remote from the suction cups on the suction head. The suction gripper is used in a manipulation system for ophthalmic lenses that encompasses ophthalmic lenses, a storage cup, a centering cup and the suction gripper.

A system for lifting a vehicle via multiple slings comprises a vehicle not engineered with structural facility to withstand lifting forces, including a frame which unmodified will deform in response to vertically imposed lifting forces, frame reinforcing elements affixed to the frame at selected locations which are subject to lifting deformation, at least two lifting members at spaced-apart forward frame locations, at least two lifting members at spaced-apart rearward frame locations, and a plurality of elongate slings extending respectively between each lifting member and a common lifting vertex. Each lifting member has an enlarged lower base portion rigidly affixed to the frame and an upper lifting portion. The frame reinforcing elements resist deformation of the frame in response to vertically imposed lifting forces. The enlarged base portions of the lifting members apply forces over a correspondingly enlarged area of the frame and the reinforcing elements without deforming the frame.

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.

To enable positioning a robot arm and a workpiece with high accuracy while reducing vibrations of a camera. According to the claimed invention for this purpose, a robot station 100 includes a pedestal 103 to which robot arms 101 and 102 are fixed, a camera 106 which images an area including a working area 209 of the pedestal 103, and a booth 104 to which the camera 106 is fixed. The pedestal 103 is fixed to a floor surface, and the booth 104 is fixed to the floor surface without contacting the pedestal 103. The booth 104 is formed in the shape of a rectangular parallelepiped having a short side parallel to a workpiece conveying direction T and a long side perpendicular to the workpiece conveying direction T in a plan view. In the booth 104, the length of the long side y of the booth 104 is set to not less than the sum of a maximum length by which the robot arms 101 and 102 protrude from the pedestal 103 in a direction perpendicular to the workpiece conveying direction T and the length in the direction perpendicular to the workpiece conveying direction T of the pedestal 103 in a plan view.

A method of replacing a generator of a wind power installation. The generator is provided in the interior of a pylon of a wind power installation and the pylon has a door opening. An exchanging cross beam is fixed by way of a first fastening point to a crane hook of a mobile crane. A first end of the cross beam is introduced with a second fastening point through the door opening into the pylon. The transformer to be replaced is fixed to the second fastening point of the first end. A compensating weight is fixed at the second fastening point to the second end of the cross beam. The second end of the cross beam is tilted or inclined until the transformer is at the height of the door opening and the crane hook is moved until the transformer to be replaced is outside the door opening.

A tool for lifting a tile from the bore of a chimney or other vertical opening has pivotably connected arms. Jaws at the lower ends of the arms are offset from a lifting point of the tool and optionally, from the pivot point. An actuating mechanism closes the jaws. One mechanism comprises a screw that moves a nut and one or more toggle elements connected thereto. Another mechanism comprises toggle elements which connect to the upper ends of arms and pull on them when upward force is applied at a lifting point. A releasable latch keeps the arms of tool spaced apart while a tile wall is being engaged. At least one jaw is a thin plate; preferably the opposing jaw is pivotable. Both jaws may be angled relative to the principal axis of the tool.

A containment system to safely store a waste scoop includes: an outer receptacle including a bottom surface, at least one side wall, an opening and a first coupling element; an inner receptacle including a bottom surface and at least one side wall housed within the outer receptacle and including an opening, wherein the inner receptacle is removable from the outer receptacle via the opening of the outer receptacle; a scoop assembly including a scoop, a handle, and a lid, wherein the scoop is housed within the inner receptacle and is removable from the inner receptacle via the opening of the inner receptacle; a compartment including a second coupling element for connecting the compartment to the outer receptacle via the first and second coupling elements; and a third and fourth coupling element to secure a planar surface of the lid to cover the opening of the outer receptacle.

A clevis type slip hook or grab hook includes a safety latch which is held in position by a biased pin that may be axially extended to move the latch between a latching and unlatching position to close or open the slot in the slip hook. The latch is comprised of a closure member in the form of a plate having an elongate edge that fits in the hook slot between the tip end and shank end of the hook.

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.

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.

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 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.

Disclosed is a zirconium alloy material having high corrosion resistance regardless of thermal history during its manufacturing process. The zirconium alloy material is obtained by providing a zirconium alloy containing on the mass basis: 0.001% to 1.9% of Sn, 0.01% to 0.3% of Fe, 0.01% to 0.3% of Cr, 0.001% to 0.3% of Ni, 0.001% to 3.0% of Nb, 0.027% or less of C, 0.025% or less of N, 4.5% or less of Hf and 0.16% or less of O with the remainder being inevitable impurities and zirconium, being formed of a bulk alloy and a surface layer, in which the surface layer has a plastic strain of 3 or more or a Vickers hardness of 260 HV or more and an arithmetic mean surface roughness Ra of 0.2 μm or less.

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.

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.

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 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.

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.