Abstract: An embodiment of the present invention takes the form of a system that allows for simultaneously assembling or disassembling multiple segmented nuclear fuel rods (hereinafter “segmented rods”). An embodiment of the present invention, may receive, secure, and move the segmented rods into a position that allows for performing the tasks of either assembly or disassembly, allowing for an operator to use a tool to complete the aforementioned tasks.

Abstract: A device for supporting nuclear fuel plates (4) with a longitudinal axis (X) including a bottom (6) forming a lower longitudinal end of the supporting device and a lid (8) forming an upper longitudinal end of the supporting device, the bottom (6) and the lid (8) being rigidly connected to each other through a central connecting means and peripheral connecting means, a plurality of upper means (18) for supporting the plates (4) attached to the lid (8), and a plurality of lower means (16) for supporting the plates (4) attached to the bottom (6), ensuring elastic support of the longitudinal ends of the plates (4) in a direction of the width (R) of the plate (4) and allowing free deformation of said longitudinal ends in the direction of the thickness (T) of the plate.

Abstract: A new interface between the cladding and the stack of pellets in a nuclear fuel rod. According to the invention, an interface joint made of a material transparent to neutrons, in the form of a structure with a high thermal conductivity and open pores, adapted to deform by compression across its thickness, is inserted between the cladding and the stack of fuel pellets over at least the height of the stack. The invention also relates to associated production methods.

Abstract: A device and technique for placing and moving a ferromagnetic element in an annulus between coaxially arranged cylindrical tubes. The device includes an electromagnetic ram moved along the interior of a cylindrical tube. The movable ferromagnetic element is magnetically coupled to the electromagnetic ram and moved by magnetic force to a location in the annulus defined by the tubes and magnetically coupled to the electromagnetic ram for movement in and removal from the annulus.

Abstract: The present invention relates to a fuel assembly (10) and a tubular element (32, 32′) for a nuclear boiling water reactor. The fuel assembly (10) comprises a plurality of full-length fuel rods (14), at least one part-length fuel rod (15) and at least a tubular element (32, 32′), which is arranged above the part-length fuel rod (15) in the fuel assembly (10). A cooling medium flows, during the operation of the boiling water reactor, upwardly through the fuel assembly (10) in order to cool the fuel rods (14, 15). A part of the cooling medium flow is guided into the tubular element (32, 32′) through at least one inlet opening (34, 34′) and out through at least one outlet opening (36).

Abstract: The invention relates to a fuel assembly for a boiling water reactor which is adapted, during operation of the reactor, to allow water to flow upwards through the fuel assembly while absorbing heat from a plurality of fuel rods, whereby part of the water is transformed into steam. The fuel assembly comprises a steam channel through which the steam flows through the fuel assembly. The steam channel (16a, 16b, 16c, 16d) consists of an empty volume which at least extends through part of the fuel assembly. The fuel assembly is designed such that the water and the steam are brought to rotate around the steam channel whereby the water is thrown away from the steam channel whereas the steam which is separated from the water flows upwards through the steam channel.

Abstract: A fuel assembly for a boiling water reactor which is designed to allow water, during operation of the reactor, to flow upwards through the fuel assembly while absorbing heat from a plurality of fuel rods, whereby part of the water is transformed into steam. The fuel assembly comprises a first steam pipe (10a) arranged with its longitudinal axis parallel to the longitudinal axis of the fuel assembly and the steam pipe comprises an inlet for the steam arranged in the first end of the steam pipe and an outlet for the steam arranged in the second end of the steam pipe. The fuel assembly also comprises a second steam pipe (10b) arranged above and at a distance from the first steam pipe such that an opening is formed between the steam pipes. The outlet of the first steam pipe has a diameter which is larger than the diameter of the inlet of the second steam pipe.

Abstract: A Critical Channel Power (CCP) enhancement system is provided for a pressurized fuel-channel-type water-cooled nuclear reactor of the type adapted to be refuelled on-line by the insertion and removal of fuel bundles onto and from of a plurality of said fuel channel assemblies, each of said fuel channel assemblies. A means is provided for interlocking fuel bundles into pairs having their fuel elements aligned, thereby lowering the hydraulic resistance in the fuel channel and enhancing CCP. The means for interlocking prevents misalignment of the paired bundles during their residence time inside the reactor due to continuous rocking and vibration of the fuel bundles exposed to very high coolant mass flow rate and misalignment due to axial separation of bundles impacting upon one another during fuelling operations.

Abstract: A fuel assembly for a boiling water reactor comprising a plurality of fuel units, stacked on top of each other, each of which comprising a plurality of fuel rods extending vertically between a top tie plate and a bottom tie plate, and means for keeping the fuel elements together. The fuel elements are surrounded by a fuel channel with a substantially square cross section. At least two of the fuel units differ from each other in regard to fuel distribution or free flow area.

Abstract: A fuel assembly for a boiling water reactor comprising a plurality of fuel units (3a, 3b, 3c, 3d), stacked on top of each other, each one comprising a top tie plate (5), a bottom tie plate (6) and a plurality of fuel rods (4a, 4b, 4c) arranged between the top tie plate and the bottom tie plate. The fuel units are surrounded by a fuel channel (9) with a substantially square cross section. At least some of the fuel units comprise fuel rods with different diameters and different fuel quantities. The fuel rods are adapted such that fuel quantity and lattice space are optimized laterally and axially in the fuel assembly.

Abstract: The present invention relates to a fuel assembly with a substantially square cross section for a light-water reactor. The light-water reactor comprises a plurality of fuel rods (4) extending between a top tie plate (5) and a bottom tie plate (6). A fuel rod (4) comprises a cladding tube (7a) with a first and a second end which surround a column with fissionable material (7b). According to one aspect of the invention, at least one fuel rod (4) is provided with an axial gap (19) in the fissionable material (7b), such that fissionable material (7b) is arranged on both sides of the axial gap (19) in the fuel rod (4).

Abstract: The present invention relates to a fuel assembly for a light-water nuclear reactor with a substantially square cross section which comprises fuel rods (4) extending between a bottom tie plate (16) and a top tie plate (17). A coolant is adapted, during operation, to flow upwards through the fuel assembly. According to one aspect of the invention, the fuel assembly comprises a plurality of fuel units (3) stacked on top of each other, wherein each fuel unit (3) comprises a plurality of fuel rods (4) extending between a top tie plate (17) and a bottom tie plate (16). The fuel units are arranged attached to a support structure (4a, 14, 14a, 14b) extending through the whole fuel assembly such that axial gaps are formed between the fuel units (3). One of the tie plates is freely movable relative to the support structure.

Abstract: A fuel assembly for a boiling water reactor comprises a plurality of first full-length fuel rods arranged in an orthogonal lattice, wherein each fuel rod is included in two rows of fuel rods perpendicular to each other, and a number of second fuel rods arranged in parallel with the first fuel rods and having the length considerably smaller than the length of the first fuel rods. The second fuel rods are arranged in the lower part of the fuel assembly in the space which is formed between a number of first fuel rods located adjacent to each other, that is, in a position which does not belong to the orthogonal lattice.

Abstract: A nuclear fuel element for use in a gas cooled nuclear reactor, such as a Magnox reactor, has a plurality of fuel pin supports defining an element axis passing through the supports. Suspended between the supports are a plurality of fuel pins formed by a stack of oxide fuel pellets within a metal tube. Connected between the supports are a number of elongate members, for example tubular rods, which extend parallel to the axis and are disposed around the fuel pins. One or more of the tubular rods incorporates a doping material, such as gadolinia.

Abstract: A nuclear propulsion reactor. A pressure vessel is provided with a reactor core that is surrounded by a radial reflector. Nuclear fuel elements in the core are formed from a hexagonal housing made from a high performance moderator and having a plurality of axial bores that extend the full length of the housing. A stack of nuclear fuel compacts having axial bores for coolant flow is received in the central axial bore of the housing. Hollow lithium hydride slugs are received in the bores at the corners of the housing. A rocket nozzle is attached to one end of the pressure vessel. Coolant/propellant flows into a passageway around the rocket nozzle for cooling thereof, upward through bores in the reflector and through the hexagonal housings of the fuel elements, downward through the bores in the nuclear fuel compacts and then out the rocket nozzle where propulsive thrust is produced.

Abstract: A modular fuel assembly for a nuclear thermal engine includes a plurality of fuel elements each having a fueled, truncated conical shell and an unfueled peripheral lip at the base of the shell with radial passages there-through. The fuel elements are nested with the lips seating one on top of another to form a stack of fuel elements with frusto-conical flow passages between the shells of adjacent fuel elements which are divided into channels by ribs on the conical shells. The stack of fuel elements is mounted in a cylindrical housing with the bases of the shells facing a central inlet opening at one end of the housing. Propellant enters the central inlet opening, is deflected radially outward by a deflector into an annular flow distribution channel from which it flows radially inward through the passages in the fuel element lips, through the flow channels of frusto-conical passages between the fueled shells where it is heated, and out through a central exhaust passage.

Abstract: A fuel bundle is disclosed in which interspersed part length fuel rods define between the end of the fuel rods and the upper tie plate void regions which are not otherwise occupied. Full length fuel rods adjacent to these regions are provided with an expanded upper plenum region which effectively increases the fuel rod diameter at the end of the upper two phase region of the fuel bundle. Under normal circumstances and a fuel bundle with only full length fuel rods, such an expansion of the upper regions of the fuel rods would cause unacceptable pressure drop. Where such expansion occurs adjacent the vacated volumes created by the part length fuel rods, unacceptable pressure drop does not occur. Consequently, and with the expanded plenum volume, a longer length of active fuel pellets can be accommodated within the full length fuel rods.

Abstract: Fuel management in a boiling-water nuclear reactor involves arranging fuel bundles in upper and lower matrices of the reactor core. During a refueling operation, some bundles in the upper matrix are removed and retired, while fresh bundles are inserted in the lower matrix and some bundles originally in the lower matrix are transferred to the upper matrix. In the transfer, fuel bundles are inverted so that included fuel rods in the lower matrix have their plenums oriented downward, while fuel rods in the upper matrix have their plenums oriented upward. This method provides greater flexibility in repositioning fuel bundles for longer burnups and lower high-level waste. In particular, problems with axial spectral variations in neutron flux can be compensated for using the disclosed refueling procedure.

Abstract: A nuclear reactor with a recirculating heat transfer fluid has a bi-level core which provides enhanced flexibility in fuel arrangement. The bi-level core includes a first core, a plurality of steam separators disposed above the first core, and a second core disposed above the steam separators all inside a single pressure vessel. The steam separators receive a steam and water mixture from the first core and separate the water from the steam. The separated steam is channeled to the second core which cools the second core resulting in the generation of superheated steam. Preferably, fuel bundles of the second core are arranged in vertical alignment with fuel bundles of the first core. This permits a fuel bundle of the first core to be accessed by removing only the adjacent fuel bundle of the second core. During refueling operations, fuel bundles can be shifted from one core to the other, providing additional flexibility in arranging units at various states of burnup.

Abstract: In a nuclear fuel bundle for a boiling water reactor, the prior art suggested concept of tapered fuel rods forming the bundle array is disclosed in a practical design including a fuel bundle and an improved associated spacer utilized in the upper two phase region of the fuel bundle. A tapered fuel rod is utilized having a large diameter bottom tube for holding corresponding large diameter fuel pellets at the fuel rod bottom, a smaller diameter top tube for holding correspondingly smaller diameter pellets at the top of the fuel rod, and a bell reducer situated between the large diameter lower fuel tube and the smaller diameter upper fuel tube. This bell reducer tapers from the large outside diameter of the lower fuel tube and the smaller outside fuel diameter of the upper fuel tube and forms a smooth transition between the large and small diameter sections of the fuel rod. An improved fuel rod spacer is disclosed for use with the upper and smaller tube portions of the fuel rods.

Abstract: In accordance with the present invention, a nuclear reactor with a recirculating heat transfer fluid has a bi-level core which provides enhanced flexibility in fuel arrangement. The bi-level core includes two sets of fuel units, one set arranged on a first level, the other set arranged on a second level. Preferably, fuel units of the second level are arranged in vertical alignment with fuel units of the first level. This permits a fuel unit of the first level to be accessed by removing only the adjacent fuel unit of the second level. During refueling operations, fuel units can be shifted from one level to the other, providing additional flexibility in arranging units at various stages of burnup. Preferably, fuel units of the first level are inverted relative to the fuel units of the second level.

Abstract: A reactor core includes upper and lower matrices of fuel bundles. Fuel rods in the upper matrix have their plenums oriented upward, while fuel rods in the lower matrix have their plenums oriented downward. Refueling involves removal of a first bundle in the upper matrix, removal and retirement of the bundle in the lower matrix directly below the original position of the first bundle, inversion and installation of the first bundle in the lower matrix, and installlation of a new bundle in the upper matrix. The new bundle is installed plenum-side up. The bi-level core provides greater flexibility in repositioning fuel bundles for longer burnups and lower high-level waste. In particular, problems with axial spectral variations in neutron flux can be compensated using the disclosed core arrangement and refueling procedure.

Abstract: An isotopic heat source is formed using stacks of thin individual layers of a refractory isotopic fuel, preferably thulium oxide, alternating with layers of a low atomic weight diluent, preferably graphite. The graphite serves several functions: to act as a moderator during neutron irradiation, to minimize bremsstrahlung radiation, and to facilitate heat transfer. The fuel stacks are inserted into a heat block, which is encased in a sealed, insulated and shielded structural container. Heat pipes are inserted in the heat block and contain a working fluid. The heat pipe working fluid transfers heat from the heat block to a heat exchanger for power conversion. Single phase gas pressure controls the flow of the working fluid for maximum heat exchange and to provide passive cooling.

Abstract: A high temperature nuclear control rod assembly comprises a plurality of substantially cylindrical segments flexibly joined together in succession by ball joints. The segments are made of a high temperature graphite or carbon-carbon composite. The segment includes a hollow cylindrical sleeve which has an opening for receiving neutron-absorbing material in the form of pellets or compacted rings. The sleeve has a threaded sleeve bore and outer threaded surface. A cylindrical support post has a threaded shaft at one end which is threadably engaged with the sleeve bore to rigidly couple the support post to the sleeve. The other end of the post is formed with a ball portion. A hollow cylindrical collar has an inner threaded surface engageable with the outer threaded surface of the sleeve to rigidly couple the collar to the sleeve. the collar also has a socket portion which cooperates with the ball portion to flexibly connect segments together to form a ball and socket-type joint.

Abstract: A modular fuel assembly has a plurality of axially stacked subassemblies. The stacked subassemblies includes upper and lower subassemblies which incorporate top and bottom nozzles, and a plurality of intermediate subassemblies disposed between the upper and lower subassemblies. Each subassembly includes a plurality of elongated guide thimble segments, a plurality of fuel rod segments and a pair of support grids mounted to the guide thimble segments and supporting the fuel rod segments. The guide thimble segments of the upper and lower subassemblies are releasably mounted to the respective top and bottom nozzles thereof.

Abstract: An absorber rod for nuclear reactors with a pile of spherical fuel elements, which is inserted directly into the pile, in order to affect the prevailing neutron flux by absorber material located in an annular gap between two concentric cylindrical rod elements. The absorber rod has concentric rod elements arranged in pairs, a common rod tip and common connecting pieces. The rod elements are cooled by flow of gas and the inner cylindrical rod element performs the support function, i.e., it absorbs and transmits forces and moments originating in the movements of the rod during insertion and extraction.

Abstract: A nuclear fuel element comprising an elongate block of refractory material having a generally regular polygonal cross section. The block includes parallel, spaced, first and second end surfaces. The first end surface has a peripheral sealing flange formed thereon while the second end surface has a peripheral sealing recess sized to receive the flange. A plurality of longitudinal first coolant passages are positioned inwardly of the flange and recess. Elongate fuel holes are separate from the coolant passages and disposed inwardly of the flange and the recess. The block is further provided with a plurality of peripheral second coolant passages in general alignment with the flange and the recess for flowing coolant. The block also includes two bypasses for each second passage.

Abstract: A flow exchange element is presented which lowers temperature gradients in fuel elements and reduces maximum local temperature within high temperature gas-cooled reactors. The flow exchange element is inserted within a column of fuel elements where it serves to redirect coolant flow. Coolant which has been flowing in a hotter region of the column is redirected to a cooler region, and coolant which has been flowing in the cooler region of the column is redirected to the hotter region. The safety, efficiency, and longevity of the high temperature gas-cooled reactor is thereby enhanced.