Abstract:
Die Erfindung betrifft ein Brennelement (1) eines Siedewasserreaktors, mit einem von Abstandhaltern (3) lateral gehaltenen und von einem Brennelementkasten (9) umfassten Brennstabbündel, wobei von den Aussenwänden (15) eines Abstandhalters Noppen (19) vorstehen, die einen Minimalspalt zwischen der jeweiligen Aussenseite (15) eines Abstandhalters (3) und dem Brennelementkasten (9) gewährleisten, und wobei die Schlüsselweite eines Abstandhalters (3) kleiner ist als die lichte Weite des Brennelementkastens (9). Die Neuerung besteht darin, dass dass ein Abstandhalter (3) von einer seitlich auf ihn wirkenden Kraft derart in einer aussermittigen Lage gehalten ist, dass ein äusserer Spalt (22), der zwischen einer der Aussenseite (18) einer Kernzelle (2) zugeordneten Aussenseite (15) des Abstandhalters (3) und dem Brennelementkasten (9) vorhanden ist, enger ist als ein diesem gegenüberliegender, dem Zentrum bzw. einem dort vorhandenen Steuerelement zugewandter Spalt (23).
Abstract:
A cooling water tube for use in a fuel rod bundle for a nuclear reactor is provided in accordance with a first aspect of the present invention. The tube has a center section, a first end section disposed at one end of the center section, and a second end section disposed at a second end of the center section. The cooling water tube is formed of a single piece of tubing and has no seams or welds between the sections. A method for manufacturing the cooling water tube is also provided in accordance with another aspect of the present invention.
Abstract:
The invention relates to the production of construction materials and can be used for producing concrete mixture used for building constructions exhibiting radiation protection properties. The inventive concrete radiation protection mixture comprises soluble glass, alkaline fluorosilicate and a fine aggregate in the form of a lead-containing broken glass with fractions ranging from 1.25 to 0.63 mm, from 0.63 to 0,32 mm and from 0.32 to 0.14 mm, a filler in the form of powdered glass of kinescope funnel whose specific surface area ranges from 3500 to 5000 cm /g, a coarse aggregate in the form of broken glass of kinescope tubes with fractions ranging from 5 to 25 mm and from 2.5 to 1.25 mm and a fine aggregate in the form of broken glass of kinescope tubes, according to the following ingredient ratio: 5-8 mass % of soluble glass, 0.01-0,1 mass % of alkaline fluorosilicate, 20-25 mass % of powdered glass of kinescope tubes, the coarse aggregate in the form of broken glass of kinescope tubes with the following fraction makeup: 25-30 mass % of 5-25 mm and 10-15 mass % of 2.5-1.25 mm, and a fine aggregate in the form of broken glass of kinescope funnels having the following fraction makeup: 9-12 mass % of 1.25-0.63 mm, 9-12 mass % of 0.63-o.32 mm, 9-12 mass % of 0.32-0.14 mm, the rest being water. The inventive concrete mixture can be used at a temperature ranging from 60 DEG C to +200 DEG C, the production thereof does not require sophisticated technology and makes it possible to recycle waste glass of kinescope.
Abstract:
Passive emergency cooling in response to a loss of coolant accident (LOCA) in a PWR, having an integral reactor pressure vessel incorporating the steam generators and housed in a small high pressure containment vessel, is provided by circulating cooling water through the steam generators and heat exchangers in an external tank to cool the reactor vessel at a rate sufficient to lower the pressure in the reactor vessel below that in containment the reverse mass flow out of the reactor vessel and keep the reactor core covered without the addition of makeup water. Suppression tanks inside the small high pressure containment structure limit peak blowdown pressure in containment and provide flood-up water and gravity fed makeup water to cool the core. Diverse cooling is provided by natural circulation of air, and if needed, water, over the spherical containment structure.
Abstract:
An apparatus (5) for splitting pipes (11) comprises means (1) for forming a longitudinal cut of the pipe (11), and diverging means (2) for opening up the cut pipe to expose the pipe interior. A method for splitting pipes (11) comprises the steps of forming a longitudinal cut of the pipe and opening out the cut pipe to expose its interior.
Abstract:
A method and apparatus for driving nuclear reactions in a controlled manner within a shaped cavitation nuclear reactor or CNR is provided. The shape of the CNR is generally cylindrical, with the central region of the reactor having a substantially smaller diameter than either end portion. Due to this shape, the central reactor region undergoes enhanced cavitation with numerous reaction sites being in close proximity to the surface of the reactor's central region. As a result, the shaped reactor configuration is well suited for use as a photon/particle source. Attached to either end of the CNR is a driver assembly, the driver assemblies being used to couple acoustic energy into the reactor. The CNR may be contained within a high pressure enclosure fabricated from a material capable of withstanding the high reactor operating temperatures. Preferably the high pressure enclosure is encased in one or more layers of thermal insulation, followed by an outer enclosure. Coolant, fed through one or more nozzles, impinge upon the outer surface of the reactor thereby providing reactor cooling as well as a means of generating a high pressure fluid such as vapor or steam. The high pressure fluid is, in turn, coupled to an energy conversion system such as a steam turbine, heater radiator, steam piston motor, or other heat exchanger. The reactor system may include one or more static stress amplitude modulators which provide a means of simultaneously applying a static force with the dynamic forces applied by the drivers.
Abstract:
A new and improved system for facilitating heat removal from a cavitation nuclear reactor. Cavitation nuclear reactors generally have a reaction chamber within which the cavitation nuclear reactions take place. Cavitation nuclear reactions are driven by acoustic energy. In order to generate the necessary acoustic energy, drivers are connected to the reaction chamber. This new and improved system utilizes two independant circuits to increase the efficiency of the cavitation nuclear reactors. One circuit serves to remove the energy from the interior of the reaction chamber at as high a temperature as possible. The other circuit acts to cool down the drivers so as to allow the drivers to operate within the optimal operating temperature range. Additional fins or extensions are added to protrude from the outer surface of the chamber, or alternatively, the outer surface of the chamber is corrugated to increase the amount of heat flow from the interior of the chamber.
Abstract:
A method and apparatus for driving nuclear reactions in a controlled manner within a cavitation nuclear reactor or CNR is provided. In general, the CNR is comprised of a solid material and, more particularly, comprised of a fuel material interspersed within a host material. The CNR can utilize any of a variety of different shapes. Energy, typically in the form of acoustic energy, is driven into the CNR with one or more drivers in order to create a pressure intensity pattern within the reactor. As a result of the pressure intensity pattern, at numerous locations within the reactor the energy is large enough to form small cavities or bubbles. Due to the phenomena of cavitation, the applied energy causes the newly formed bubbles to oscillate, undergoing a period of expansion followed by a period of bubble collapse. The velocity of the spherically converging material associated with the cavitation cycle, often times reaching supersonic velocities, is sufficient to achieve a density and temperature in excess of that required to drive a variety of different nuclear reactions including fusion, fission, spallation, and neutron stripping. If desired, an external heat source can be used to heat the material comprising the CNR, thereby promoting the desired nuclear reactions. In a specific embodiment, the CNR is driven at a frequency that either substantially matches a resonant frequency of the CNR or substantially matches an integer multiple of a resonant frequency.
Abstract:
A top mount canopy seal mechanical clamp assembly (20) for repair of a leaking canopy seal weld (16) between a nuclear reactor head penetration nozzle (12) and a mating part (14) has an annular housing (24) with insert support halves (28) and (30) for surrounding the nozzle. A top plate (34) is urged toward the support halves and housing by Belleville washers mounted on cap screws (42) threaded in bores (44) of the housing. A Grafoil seal annulus (22) is compressed by the clamping action against the canopy seal weld (16) to create a Grafoil leak stopping seal at the weld.
Abstract:
A support grid for laterally maintaining the relative position of elongated fuel elements within a fuel assembly for use within a core of a nuclear reactor. The grid is formed in the shape of a lattice with the intersecting lattice members defining a plurality of cells, most of which respectively support the nuclear fuel elements. The reamining cells support nuclear control rod guide tubes and instrumentation thimbles. The cells supporting the nuclear fuel elements are provided with diagonally positioned springs on two, adjacent walls. The springs support the fuel elements against dimples which protrude from the opposite cell walls. The adjacent, diagonal springs in each fuel element cell are inclined in opposite directions. The walls of the cells supporting the control rod guide tubes are embossed along their height at the locations intermediate the intersection between adjoining walls with a concave notch having a curvature which conforms to the outside surface curvature of the control rod guide tubes. The grid is provided with mixing vanes which are positioned in a symmetrical, regional pattern, with the pattern varying between adjacent regions, and configured such that the hydraulic forces across the center of the grid are balanced. The grid is reinforced with welds at the mid point of the intersection of the lattice straps.