Abstract:
Disclosed are apparatus and methods for storing or transporting spent nuclear fuel. In one embodiment, a container (10) for storing spent nuclear fuel comprises a plurality of elongated tubes (2, 4, 6, 7) that receives spent nuclear fuel rods. Each tube (2, 4, 6, 7) has four sidewalls and four corners defining a rectangular cross section. The plurality of tubes (2, 4, 6, 7) is arranged in an alternating pattern. An attachment means attaches together the plurality of tubes (2, 4, 6, 7) at the corners so that two adjacent sidewalls (64, 66, 68, 70) of adjacent tubes (2, 4, 6, 7) are substantially aligned.
Abstract:
Les assemblages de combustible (5) comportent une structure résistante rigide (21) constituée par l'embout inférieur (16) et l'embout supérieur (17) de l'assemblage de combustible reliés entre eux par au moins deux éléments longitudinaux de liaison rigide (22). La longueur totale de l'ossature de l'assemblage de combustible est inférieure à la distance verticale entre une face supérieure de la plaque inférieure de cœur (7) et une surface inférieure de la plaque supérieure de cœur (8). L'embout supérieur (17) des assemblages de combustible ne comporte pas de ressort d'appui à lames. L'embout inférieur (16) et l'embout supérieur (17) de chacun des assemblages de combustible comportent des ouvertures de positionnement dans lesquelles sont montés des dispositifs de serrage élastique de pions de positionnement (18, 19) respectifs de la plaque inférieure de cœur (7) et de la plaque supérieure de cœur (8). Les crayons de combustible (13) des assemblages de combustible sont fixés sur l'embout inférieur (16). L'ossature (5a) de l'assemblage de combustible comporte, à l'intérieur de la structure résistante (21), une pluralité de tubes-guides (15) montés glissants dans l'un au moins de l'embout inférieur (16) et de l'embout supérieur (17) de l'assemblage de combustible et une pluralité de grilles-entretoises (14) de maintien transversal des crayons montées glissantes dans la direction longitudinale axiale sur les éléments longitudinaux de liaison (22) de la structure résistante (21).
Abstract:
A nuclear power generator having a nuclear fuel assembly which is periodically adjacent first to a first nuclear reactor containing fresh nuclear fuel where the fuel assembly achieves a supercritical state, and then adjacent to a second nuclear reactor containing spent nuclear fuel where delayed neutrons resulting from the supercritical state of the fuel assembly cause a supercritical state in the spent fuel thereby releasing heat. A nuclear powered steam expansion engine capable of converting nuclear energy to mechanical work by periodically bringing into proximity two nuclear fuel assemblies within a piston and cylinder assembly, thus making the fuel assemblies successively supercritical and subcritical in cyclical fashion, with associated cyclical heating, periodically injecting water into the resultant heated cylinder, which water is converted to steam which expands, drives the piston, and produces mechanical work, recycling the expanded steam by adding additional heat during an exhaust stroke, and using the recycled steam to drive a turbine system.
Abstract:
A system (10) for the passive dissipation of the heat from the interior (8) of a containment structure (3, 9) of a nuclear reactor (2), which would develop particularly in the case of accidents, comprises a first metal wall (11) lining the side and/or top walls (5, 6) within the said containment structure (3), a second metal wall (16) intermediate between the said first metal wall (11) and the said side and/or containment walls (5, 6), a sealed interspace (18) confined by the said first and second metal walls (11, 16) and containing a heat collection fluid (22) and means (24) for the passive dissipation of heat from the said interspace (18).
Abstract:
Disclosed are apparatus and methods for storing or transporting spent nuclear fuel. In one embodiment, a container (10) for storing spent nuclear fuel comprises a plurality of elongated tubes (2, 4, 6, 7) that receives spent nuclear fuel rods. Each tube (2, 4, 6, 7) has four sidewalls and four corners defining a rectangular cross section. The plurality of tubes (2, 4, 6, 7) is arranged in an alternating pattern. An attachment means attaches together the plurality of tubes (2, 4, 6, 7) at the corners so that two adjacent sidewalls (64, 66, 68, 70) of adjacent tubes (2, 4, 6, 7) are substantially aligned.
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 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 nuclear power generator having a nuclear fuel assembly which is periodically adjacent first to a first nuclear reactor containing fresh nuclear fuel where the fuel assembly achieves a supercritical state, and then adjacent to a second nuclear reactor containing spent nuclear fuel where delayed neutrons resulting from the supercritical state of the fuel assembly cause a supercritical state in the spent fuel thereby releasing heat. A nuclear powered steam expansion engine capable of converting nuclear energy to mechanical work by periodically bringing into proximity two nuclear fuel assemblies within a piston and cylinder assembly, thus making the fuel assemblies successively supercritical and subcritical in cyclical fashion, with associated cyclical heating, periodically injecting water into the resultant heated cylinder, which water is converted to steam which expands, drives the piston, and produces mechanical work, recycling the expanded steam by adding additional heat during an exhaust stroke, and using the recycled steam to drive a turbine system.
Abstract:
A fuel assembly for a nuclear reactor is described, the fuel assembly including: a plurality of fuel pins (12) extending substantially parallel to the axis of the assembly and to each other; at least two structural grids spaced apart from each other, the grids being in contact with said fuel pins (12) and maintaining said fuel pins substantially mutually parallel and preventing contact therebetween, wherein the fuel assembly further comprises at least one mixing grid (50) situated intermediate said at least two structural grids, the fuel assembly being characterised in that said mixing grid (50) is positioned and fixedly located out of substantial contact with said fuel pins (12), the mixing grid also having turbulence inducing means (61) to promote turbulence in a coolant (62) flowing through said fuel assembly in use and in that the mixing grid is formed from sheet metal wherein the plane of the metal sheet from which the mixing grid is formed lies in a plane which is transverse to the axis of the fuel pin assembly.
Abstract:
The invention concerns a nuclear reactor, in particular a boiling-water reactor, containing fuel elements and a catalytic material designed to eliminate oxidizing agents. The invention calls for the catalytic material to form part of the fuel elements. For instance, the fuel elements or parts or them may be coated with the catalytic material or they may consist of an alloy which contains the material.
Abstract:
An efficient compact nuclear fusion reactor for use as a neutron source or energy source is described. The reactor comprises a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the chamber. The plasma confinement system is configured so that a major radius of the confined plasma is 1.5m or less. The toroidal magnetic field is operated 5T or less and the plasma current is 5 MA or less. Despite this, α-particles generated are confined in the plasma.