Abstract: A fast reactor core includes a sodium plenum installed above the fuel. The sodium plenum is capable of reducing a void reactivity. During operation, a tip of a primary control rod is inserted in a core fuel region, and a tip of a backup control rod is arranged near an upper end of the sodium plenum.

Abstract: Disclosed is an entropy-controlled solid solution matrix BCC alloy having strong resistance to high-temperature neutron radiation damage. The entropy-controlled solid solution matrix BCC alloy includes three or more multicomponent main elements selected from the element group consisting of Zr, Al, Nb, Mo, Cr, V, and Ti selected based on a neutron absorption cross-sectional area and a mixing enthalpy. Each of the elements is included in an amount of 5 to 35 at %, and the entropy-controlled solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy in a medium-entropy to high-entropy state. In this invention, damage caused by neutron radiation is reduced, and entropy is controlled to thus ensure a solid solution matrix BCC structure having a slow diffusion speed, and accordingly, resistance to void swelling due to radioactive rays is high.

Abstract: A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.

Abstract: A fuel assembly for use in a core of a nuclear power reactor. The fuel assembly can include a frame and a plurality of elongated, extruded fuel elements supported by the frame. The frame can include a lower nozzle that is shaped and configured to mount to an internal core structure of the nuclear power reactor. Each of the fuel elements can include a fuel kernel having fuel material disposed in a matrix of metal non-fuel material, the fuel material including fissile material, and a cladding surrounding the fuel kernel. The fuel assembly can have a moderator: fuel ratio in a region of the fuel elements of 2.4 or less.

Abstract: A fuel assembly for use in a core of a nuclear power reactor. The fuel assembly can include a frame and a plurality of elongated, extruded fuel elements supported by the frame. The frame can include a lower nozzle that is shaped and configured to mount to an internal core structure of the nuclear power reactor. Each of the fuel elements can include a fuel kernel having fuel material disposed in a matrix of metal non-fuel material, the fuel material including fissile material, and a cladding surrounding the fuel kernel. The fuel assembly can have a moderator: fuel ratio in a region of the fuel elements of 2.4 or less.

Abstract: A portable nuclear fuel cartridge comprising a unitary support structure and a plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. The nuclear fuel core is integrated into the unitary support structure to collectively form a self-supporting assemblage than can be lifted as a single unit. In another aspect, the invention is a method of fueling and/or defueling a nuclear reactor utilizing a nuclear fuel cartridge that is loaded and/or unloaded from the nuclear reactor as a single unit. In another aspect, a nuclear reactor core is provided that comprises a nuclear fuel core comprising; a plurality of first nuclear fuel assemblies, each of the plurality of first nuclear fuel assemblies having a first transverse cross-sectional configuration; and a plurality of second nuclear fuel assemblies, each of the plurality of second nuclear fuel assemblies having a second transverse cross-sectional configuration that is different than the first transverse cross-sectional configuration.

Abstract: Illustrative embodiments provide a reactivity control assembly for a nuclear fission reactor, a reactivity control system for a nuclear fission reactor having a fast neutron spectrum, a nuclear fission traveling wave reactor having a fast neutron spectrum, a method of controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, methods of operating a nuclear fission traveling wave reactor having a fast neutron spectrum, a system for controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, a method of determining an application of a controllably movable rod, a system for determining an application of a controllably movable rod, and a computer program product for determining an application of a controllably movable rod.

Abstract: A nuclear fuel assembly is provided for a boiling water reactor. The nuclear fuel assembly includes a base, a head, and a bundle of full length fuel rods and partial length fuel rods, said bundle extending upwardly and longitudinally from the base to the head. The nuclear fuel assembly includes at least one clamp for longitudinally retaining a lower plug of a partial length fuel rod with respect to the base. The clamp is an additional part fitted to the base, the clamp is at least partially received in a housing provided in the base, and the clamp is assembled to the base by mechanical engagement of complementary assemblies.

Abstract: Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor.

Abstract: Illustrative embodiments provide a reactivity control assembly for a nuclear fission reactor, a reactivity control system for a nuclear fission reactor having a fast neutron spectrum, a nuclear fission traveling wave reactor having a fast neutron spectrum, a method of controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, methods of operating a nuclear fission traveling wave reactor having a fast neutron spectrum, a system for controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, a method of determining an application of a controllably movable rod, a system for determining an application of a controllably movable rod, and a computer program product for determining an application of a controllably movable rod.

Abstract: Disclosed is a tokamak reactor. The reactor includes a first toroidal chamber, current carrying conductors, at least one divertor plate within the first toroidal chamber and a second chamber adjacent to the first toroidal chamber surrounded by a section that insulates the reactor from neutrons. The current carrying conductors are configured to confine a core plasma within enclosed walls of the first toroidal chamber such that the core plasma has an elongation of 1.5 to 4 and produce within the first toroidal chamber at least one stagnation point at a perpendicular distance from an equatorial plane through the core plasma that is greater than the plasma minor radius. The at least one divertor plate and current carrying conductors are configured relative to one another such that the current carrying conductors expand the open magnetic field lines at the divertor plate.

Abstract: The invention relates to light water reactor designs in which thorium is used as fuel and in particular to designs of jacketless fuel assemblies, which make up the cores of pressurized water reactors (PWRs) such as the VVER-1000. Nuclear reactor cores containing seed and blanket subassemblies that make up the fuel assemblies are used to burn thorium fuel together with conventional reactor fuel that includes nonproliferative enriched uranium, as well as weapons-grade and reactor-grade plutonium. In the first alternative, the reactor core is fully “nonproliferative,” since neither the reactor fuel nor the wastes generated can be used to produce nuclear weapons. In the second version of the invention, the reactor core is used to burn large amounts of weapons-grade plutonium together with thorium and provides a suitable means to destroy stockpiles of weapons-grade plutonium and convert the energy released to electric power.

Abstract: A nuclear-powered plant of a portable type with a confinement section where the reaction takes place in a core having a reactive thorium/uranium-233 composition, and where an external neutron source is used as a modulated neutron multiplier for the reactor core output. The core is housed in a containment structure that radiates thermal energy captured in a multiple-paths heat exchanger. The exchanger heat energy output is put to use in a conventional gas-to-water heat exchanger to produce commercial quality steam.

Abstract: There are provided a light water reactor core which has the same levels in cost efficiency and degree of safety as those of an existing BWR under operation now, that is, which is oriented to plutonium multi-recycle having a breeding ratio near 1.0 or slightly larger and having a negative void coefficient with minimizing modification of the reactor core structure of the existing BWR under operation now, and to fuel assemblies used for the boiling water reactor. The light water reactor core having an effective water-to-fuel volume ratio of 0.1 to 0.

Abstract: Seed-blanket type nuclear reactor cores are employed to burn thorium fuel with conventional reactor fuels, including nonproliferative enriched uranium, and weapons or reactor grade plutonium. In a first embodiment, the core is completely nonproliferative in that neither the reactor fuel, nor the generated waste material, can be used to manufacture nuclear weapons. In a second embodiment of the invention, the core is employed to burn large amounts of weapons grade plutonium with the thorium, and provides a convenient mechanism by which stockpiled weapons grade plutonium can be destroyed and converted into electrical energy. The cores of both embodiments are comprised of a plurality of seed-blanket unit fuel assemblies which have centrally located seed regions that are surrounded by annular blanket regions. The seed regions contain the uranium or plutonium fuel rods, while the blanket regions contain thorium fuel rods.

Abstract: Seed-blanket type nuclear reactor cores (10,100) are employed to burn thorium fuel with conventional reactor fuels, including nonproliferative enriched uranium, and weapons or reactor grade plutonium. In a first embodiment, the core (10) is completely nonproliferative in that neither the reactor fuel, nor the generated waste material, can be used to manufacture nuclear weapons. In a second embodiment of the invention, the core (100) is employed to burn large amounts of weapons grade plutonium with the thorium, and provides a convenient mechanism by which stockpiled weapons grade plutonium can be destroyed and converted into electrical energy. The cores of both embodiments are comprised of a plurality of seed-blanket units (12, 102) which have centrally located seed regions (18,104) that are surrounded by annular blanket regions (20,106). The seed regions contain the uranium or plutonium fuel rods (22,110), while the blanket regions contain thorium fuel rods (26,118).

Abstract: Seed-blanket type nuclear reactor cores (10,100) are employed to burn thorium fuel with conventional reactor fuels, including nonproliferative enriched uranium, and weapons or reactor grade plutonium. In a first embodiment, the core (10) is completely nonproliferative in that neither the reactor fuel, nor the generated waste material, can be used to manufacture nuclear weapons. In a second embodiment of the invention, the core (100) is employed to burn large amounts of weapons grade plutonium with the thorium, and provides a convenient mechanism by which stockpiled weapons grade plutonium can be destroyed and converted into electrical energy. The cores of both embodiments are comprised of a plurality of seed-blanket units (12, 102) which have centrally located seed regions (18,104) that are surrounded by annular blanket regions (20,106). The seed regions contain the uranium or plutonium fuel rods (22,110), while the blanket regions contain thorium fuel rods (26,118).

Abstract: A reactor core for a boiling water reactor, a fuel assembly and a control rod intended for Pu multi-recycling at a breeding ratio of about 1.0, or 1.0 or more while keeping the economical or safety performance to the same level as in a boiling water reactor now under operation. The reactor has an effective water-to-fuel volume ratio of 0.1 to 0.6 by the combination of a dense lattice fuel assembly constituted of fuel rods formed by adding Pu to degraded uranium, natural uranium, depleted uranium or low concentrated uranium, and having coolants at a high void fraction of 45% to 70% and a cluster-type, Y-type or cruciform control rod.

Abstract: Seed-blanket type nuclear reactor cores (10,100) are employed to burn thorium fuel with conventional reactor fuels, including nonproliferative enriched uranium, and weapons or reactor grade plutonium. In a first embodiment, the core (10) is completely nonproliferative in that neither the reactor fuel, nor the generated waste material, can be used to manufacture nuclear weapons. In a second embodiment of the invention, the core (100) is employed to burn large amounts of weapons grade plutonium with the thorium, and provides a convenient mechanism by which stockpiled weapons grade plutonium can be destroyed and converted into electrical energy. The cores of both embodiments are comprised of a plurality of seed-blanket units (12, 102) which have centrally located seed regions (18,104) that are surrounded by annular blanket regions (20,106). The seed regions contain the uranium or plutonium fuel rods (22,110), while the blanket regions contain thorium fuel rods (26,118).

Abstract: Neptunium of minor actinide nuclides separated from spent fuel is added to fuel of reactor cores (inner reactor cores and/or outer reactor cores) of a fast reactor and americium of the separated minor actinide nuclides and rare earth elements are added to either or both of radial and axial blankets of the fast reactor for burning. Thus, the minor actinide nuclides with long half-lives can be burnt with the fast reactor core with the minimized effects of the rare earth elements. For a burner reactor, americium and rare earth elements may be added to shields for burning. Curium may be added together with americium and rare earth elements. Neptunium is added in amount of 2% to 5% by weight based on the weight of the fuel and the rare earth elements are added in an amount of 50% by weight or less based on the weight of the fuel. A Purex process is used to separate neptunium and a Truex process is used to separate americium and curium.

Abstract: The invention provides a heterogeneously loaded type of fast reactor core in which a reduced number of target fuel assemblies containing minor actinide nuclides are heterogeneously dispersed and loaded. A wrapper tube for each of the target fuel assemblies is of the same shape and size as a hexagonal wrapper tube for an ordinary core fuel assembly. Each of target fuel rods within the wrapper tube contains 20 to 50% of minor actinide nuclides, and has a diameter more reduced than that of an ordinary core fuel rod. The number of the ordinary core fuel rods loaded in the ordinary core fuel assembly is 271 while the number of the target fuel rods loaded in the target fuel assembly is 331 or 397. Thirty to 50 such target fuel assemblies are heterogeneously dispersed and loaded in the fast reactor core.

Abstract: During operation of a light water moderated and cooled nuclear reactor, rods varying the neutron energy spectrum are introduced into the core of the reactor in the course of a first phase of the cycle in order to reduce the ratio of the volume of moderator to the volume of fissile material in the core. In a second phase of the cycle the spectrum displacement rods are extracted. The rods are of a mixture of thorium energy neutrons. The rods may be of fertile material and--depleted uranium. The invention is of particular interest in PWRs.

Abstract: A core of a light-water reactor comprises a plurality of fuel assemblies each including a number of fuel rods. The fuel rod is provided with at least one area interposed between fuel areas in a clad of the fuel rod. The interposed area contains extremely reduced or substantially no fissile nuclide. At least two areas or layers with high enrichment of the fissile nuclide are formed in the axial direction of the reactor by the location of the interposed areas throughout the whole fuel assemblies arranged in the light-water reactor core.

Abstract: A fuel assembly comprises a plurality of fuel rods supported by an upper tie plate and a lower tie plate respectively at each of upper end portion ad lower end portion, and a channel box surrounding a bundle of the fuel rods and the lower tie plate. The fuel assembly forms a natural uranium region at lower end portion of effective fuel length portion. A wall thickness at a lower thick wall region of the channel box is thicker than the wall thickness at a region disposed upwardly from the lower thick wall region and between corner portions of the channel box. An upper end of the lower thick wall region is disposed from an upper side of the lower tie plate and downwardly from an upper end of the natural uranium region. A wall thickness at the corner portion of the channel box is thicker than the wall thickness at a middle portion of the side wall between the corner positions at the region locating upward from the lower thick wall region.

Abstract: A high conversion nuclear reactor core has fuel assemblies made up from large numbers of axially-extending uranium-plutonium mixed oxide fuel rods. The fuel rods are densely packed so as to give a high conversion ratio of fissile substances, preferably approaching unity. The average plutonium enrichment in the assemblies is higher in their bottom, upstream halves, than in their top downstream halves. This has the effect of reducing a potentially dangerously high void coefficient in the core.

Abstract: A method and apparatus for improving the performance of a thermal breeder reactor having regions of higher than average moderator concentration are disclosed. The fuel modules of the reactor core contain at least two different types of fuel elements, a high enrichment fuel element and a low enrichment fuel element. The two types of fuel elements are arranged in the fuel module with the low enrichment fuel elements located between the high moderator regions and the high enrichment fuel elements. Preferably, shim rods made of a fertile material are provided in selective regions for controlling the reactivity of the reactor by movement of the shim rods into and out of the reactor core. The moderation of neutrons adjacent the high enrichment fuel elements is preferably minimized as by reducing the spacing of the high enrichment fuel elements and/or using a moderator having a reduced moderating effect.

Abstract: A fuel assembly for a nuclear reactor includes a number of fuel rods filled with a fuel material. A plurality of fuel rods have a partial effective fuel area filled with a fuel material and has a portion in which enrichment of a fissile nuclide is significantly reduced or the fissile nuclide does not exist at all on an axial level including a reactor shut-down zone at which subcriticality becomes small during a reactor operation period. The other fuel rods are filled with the fuel material throughout the entire axial length thereof. The first mentioned fuel rod may be provided with a partially interposed zone or may be constructed by a fuel rod having a length shorter than that of the other fuel rod. The tube means may be arranged in the fuel assembly so as to pass the moderator therethrough.

Abstract: A fuel assembly for a nuclear reactor comprising a number of fuel rods arranged in a regular fashion in a channel box which is surrounded by water gap in a reactor core. Some of fuel rods disposed at portions facing the water gap through which no control blade is inserted or drawn out, have atomic number densities of fissionable material contained in the fuel rods. The atomic number density of each of these fuel rods is made smaller than that of the fuel rod disposed in the fuel assembly at portions other than the portions referred to above.

Abstract: A neutron reactivity control system for a LWBR incorporating a stationary seed-blanket core arrangement. The core arrangement includes a plurality of contiguous hexagonal shaped regions. Each region has a central and a peripheral blanket area juxapositioned an annular seed area. The blanket areas contain thoria fuel rods while the annular seed area includes seed fuel rods and movable thoria shim control rods.

Abstract: A fast breeder incorporating a core having a driver core region containing an enriched fissile material, an external blanket region surrounding the core region and containing a fertile material and an internal blanket region disposed within the driver core region and containing a fertile material. The internal blanket region has a thickness or axial height greater at the central portion thereof than at the peripheral portion thereof. The peripheral end of the internal blanket region opposes to the inner peripheral surface of the external radial blanket region with a portion of the core region interposed therebetween.

Abstract: The universal fuel assembly has a plurality of elongated corner posts extending longitudinally between and releasably and rigidly interconnecting top and bottom nozzles so as to form a rigid structural skeleton of the fuel assembly. Additionally, a plurality of transverse grids are supported at axially spaced locations along the corner posts and a plurality of fuel rods are supported by the grids. Certain groups of the fuel rods are spaced apart laterally from one another by a greater distance than the rest of the fuel rods so as to define a number of elongated channels extending between the top and bottom nozzles. A cluster assembly having a cluster plate with a plurality of elongated rods is adapted to be removably supported on the top nozzle with its rods extending through the channels. The rods can be a plurality of guide thimbles in the case of one cluster assembly, or a plurality of oversized fuel rods in the case of another cluster assembly.

Abstract: In a water-cooled nuclear reactor for producing energy and having seed and blanket zones, which reactor is cooled by pressurized water and contains fissile material of plutonium and uranium, the reactor is provided, in its seed zones and blanket zones, with a plutonium composition such as obtained from light water power plant reactors after a normal service life and recycle, and with fuel elements whose geometry in the seed and blanket zones, with respect to the coolant water, is selected to produce an epithermal neutron spectrum.

Abstract: The invention relates to a core for a nuclear reactor cooled with water under pressure.The core comprises a first group of zones (1, 2) extending over its entire height and over a fraction of its transverse section where the fuel rods contain mainly enriched uranium oxide, and a second group of zones (3) inserted between the zones (1, 2) of the first group where the rods contain mainly plutonium. The rods of zones (1, 2) of the first group emit neutrons and maintain the neutron reactions. The energy spectrum of the neutrons is in the thermal region in the zones (1, 2). The rods of the zones (3) of the second group are spaced at a distance which is appreciably smaller than the distance separating the rods of the zones (1, 2) so that the neutrons produced therein are in the high energy region.The invention applies, in particular, to nuclear reactors with spectral shift control.

Abstract: A fast breeder which is formed with a driver core region having an enriched nuclear fuel substance and allowing liquid metal acting as a coolant to pass therethrough and with a blanket region surrounding the periphery of the driver core region. A reactor stopping control rod to be inserted downward into the driver core region has an axially uniform density of boron-10. A reactor power adjusting control to be inserted downward into the driver core region has a lower density of boron-10 in a lower region than that in an upper region.

Abstract: Fuel assembly for a pressurized water nuclear reactor, comprising a peripheral zone (1) consisting of a first group of rods (2) containing mainly enriched uranium oxide and a central zone (4) consisting of a second group of rods (5) containing mainly plutonium or uranium depleted in fissile uranium. The rods of the first zone (1) are spaced sufficiently so that the neutrons are slowed down to the thermal region. The rods of the second zone (4) are spaced by a distance which is appreciably smaller so that the neutrons produced in this zone (4) are in the high-energy region. The invention applies, in particular, to nuclear reactors with spectral shift.

Abstract: A complementary shutdown device for an undermoderated nuclear reactor, comprising, inside certain arrays (3) of the core, guide tubes (7) of which the cross-section is at least equal to the sum of the cross-sections of three rods (6), and which are surrounded by at least one row of fertile rods (8), and a set of shutdown rods, the cross-section of which matches the cross-section of the guide tubes (7). The shutdown is obtained by allowing the shutdown rods, containing a neutron-absorbing material, to fall into the arrays (3) of the core, in the position of maximum insertion. The invention applies, in particular, to pressurized water nuclear reactors.

Abstract: A symmetric blanket fuel assembly forming a part of a radial blanket in a nuclear reactor core includes a first group of fuel rods which contain natural uranium and a second group of fuel rods which contain enriched uranium. The first group is surrounded by the second group in a symmetrical relationship in which the first group forms an inner, centrally-located, generally squared pattern having four sides and the second group forms an outer, peripherally-located generally squared annular pattern which surrounds the first group on all four sides thereof. Also, a plurality of guide thimbles are interspersed in spaced-apart relationship among both the first and second groups of fuel rods, preferably likewise in a squared pattern.

Abstract: To provide a lithium-containing neutron target particle for breeding tritium within the core of a nuclear reactor, including a central core formed of a stable lithium-containing compound, a surrounding buffer layer, and an outer tritium-impermeable silicon carbide coating, the core is initially sealed with an inner sealing layer of pyrolytic carbon and an outer sealing layer of stoichiometric zirconium carbide. The pyrocarbon seal protects the lithium within the core from attack from the zirconium carbide coating atmosphere, and the zirconium carbide layer prevents loss of lithium from the core when the silicon carbide coating is deposited at elevated temperatures.

Abstract: An initial charge core of a fast breeder and a method of renewing fuel in the initial charge core. The initial charge core comprises a driver core region containing a fissile material, an external blanket region containing a fertile material and surrounding the driver core region, and an internal blanket region disposed within the driver core region and containing a fertile material. The axial thickness of the internal blanket region is greater at its central portion that at the peripheral portion thereof. The internal blanket region is enriched with the fissile material. The degree of enrichment in the internal blanket region is greater than that in the driver core region.

Abstract: A method for reducing thermal striping in liquid metal fast breeder reactors by reducing temperature gradients between adjacent fuel and blanket assemblies by shuffling blanket assemblies at each refueling outage so as to progressively shuffle the blanket assemblies to the core periphery through multiple moves and to generally locate fresh blanket assemblies adjacent to exposed fuel assemblies and exposed blanket assemblies adjacent to fresh fuel. Additionally, assembly orificing is altered to provide less flow to blanket assemblies needing less flow due to an otherwise decreased temperature gradient and providing additional flow to fuel assemblies which need more flow to sufficiently reduce temperature gradients to prevent thermal striping.

Abstract: A fast breeder has a driver core region enriched with a fissile material and a blanket core region containing mainly a fertile material. The driver core region includes an inner core region and an outer core region surrounding the inner core region. The volume of the inner core region is selected to range between 30 and 70% of the volume of the driver core region. The enhancement of the fissile material in the inner core region ranges between 30 and 80% of the fissile material in the outer core region.

Abstract: A heterogeneous nuclear reactor of the seed-blanket type is provided wher the fissile (seed) and fertile (blanket) nuclear fuels are segregated axially within each fuel element such that fissile and fertile regions occur in an alternating pattern along the length of the fuel element. Further, different axial stacking patterns are used for the fuel elements of at least two module types such that when modules of different types are positioned adjacent to one another, the fertile regions of the modules are offset or staggered. Thus, when a module of one type is surrounded by modules of the second type the fertile regions thereof will be surrounded on all sides by fissile material. This provides enhanced neutron communication both radially and axially, thereby resulting in greater power oscillation stability than other axial arrangements.