摘要:
Claimed embodiments of the integral nuclear reactor relate to nuclear technology and can be used in reactors with different types of heat transfer fluids with a high boiling point, such as, for example, liquid metals, molten salts, etc. Design features of the invention embodiments claimed which have a coil heat exchanger sectioned along the secondary heat carrier circuit provides for an improvement in technical and economic features due to a decrease in metal consumption of the reactor; efficient use of the internal volume of the reactor; improved safety in case of the heat exchanger tube leaks; enabling the removal of residual heat during the time after removal of the protective plug before fuel discharge operations.
摘要:
The invention relates to the field of nuclear engineering and can be used in the manufacture of fuel rods and fuel assemblies for heavy liquid metal cooled reactors, and also in the manufacture of fuel rod simulators for use in irradiation devices designed to test the operability of real fuel assemblies. The present cladding of a fuel rod for a heavy liquid metal cooled reactor is in the form of a weldless tubular element with helically-coiled fins disposed on the outer surface of said element, which is made from a ferritic-martensitic chromium-silicon steel with a minimum ferrite grain size of 7 on the GOST 5639 scale, wherein each fin has an opening angle of from 22 to 40º (preferably from 30 to 40º) and the cross-section of the fin is in the shape of a trapezoid with rounded corners at the top of the trapezoid and smooth corners at the base of the trapezoid. Also disclosed are a fuel rod comprising the above cladding, and a fuel assembly. The technical result of the invention is an improvement in the performance characteristics of fuel rods and assemblies as a result of the long-term resistance of the cladding in the environment of a heavy liquid metal coolant such as lead or a eutectic of lead and bismuth.
摘要:
This invention relates to heat exchanger devices mostly designed for operations in the heavy liquid metal coolant medium. Its use ensures more reliable fixation of heat exchanger tubes with their simultaneous spacing. The device as defined in the first option includes at least one supporting spacer grid 1 consisting of a cylindrical shell 2 and two, three or more tiers of plates 3 and 4 spaced apart at the preset gap, while the width of each plate lies within the plane which is parallel to the shell axis; ends of all plates are fixed to the shell in such a way that plates of any tier are parallel to each other and are located at the preset gap; plates of different tiers are criss-crossed at an angle of 60 degrees when observing along the shell axles, and are fastened together at the crossing points. The device as defined in the second option includes three dividers which run through the cylinder axis; their ends are connected to the shell and are spaced at an angle of 60 degrees. 2 independent claims, 3 figures
摘要:
The invention relates to nuclear physics, and specifically to reactor fuel elements and units thereof, and particularly to the composition of solid ceramic fuel elements based on uranium dioxide, intended for and exhibiting characteristics for being used in variously purposed nuclear reactors. The result consists in a more reliable, special structure and a simple composition of uranium dioxide without heterogeneous fuel pellet additives, approaching the characteristics of a monocrystal having enhanced, and specifically exceeding reference data, thermal conductivity as temperature increases, and a simple production method thereof. The result is achieved in that pores of between 1 and 5 microns in size are distributed along the perimeters of grains in the micro-structure of each metal cluster in a nuclear fuel pellet, and in that located within the grains are pores which are predominantly nano-sized. In addition, the metal clusters comprise between 0.01 and 1.0 percent by mass. The invention provides for a method of preparing a nuclear fuel pellet, including precipitating metal hydroxides, in two stages, having different pH levels. Uranium metal is melted at a temperature exceeding 1150°C, sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200°C in a hydrogen medium until forming uranium dioxide, the structure of which includes metal clusters dispersed therein. An X-ray photon spectroscope is used for identifying the new structure of the UO2 pellet and the additional U-U chemical bond.
摘要:
The invention relates to nuclear engineering, in particular to a process of the plug and the removable block extraction from a fast reactor with a heavy liquid metal coolant. The technical result consists in extracting the plug and the removable block without fuel assemblies from the nuclear reactor using a complex of handling equipment under radiation safety conditions. The method of the plug removable block extraction involves preliminary installation of handling equipment, removing the plug from the reactor monoblock, as well as transportation and positioning of the plug in the plug shaft, unloading the removable block, its transportation and placing the removable block in the shaft for the removable block disassembly. 3 figures.
摘要:
The device pertains to instrumentation technology and can be used in energy production, metallurgy, chemical industry to determine hydrogen concentration in fluid and gas media in a wide range of temperatures and pressures. The hydrogen detector for gas and fluid media comprises a selective membrane and a housing with a potential measuring unit inside, a ceramic sensing element made of solid electrolyte with a standard electrode in its cavity, a porous platinum electrode applied to the external layer of the ceramic sensing element, a sealed lead-in tightly fixed inside the housing above the ceramic sensing element, the potential measuring unit that passes through the center hole of the sealed lead-in and the lower bushing. The ceramic sensing element is designed as the cylindrical element interlinked with the bottom, located in the lower part of the cylinder. The external cylindrical surface of the ceramic sensing element is tightly connected to the inner side surface of the housing. The standard electrode is located in the inner cavity of the ceramic sensing element. The external part of the ceramic sensing element bottom is covered with a layer of porous platinum electrode. The end of the potential measuring unit central core is brought out to the standard electrode. The lower bushing designed as a tube is connected to the lower part of the housing from the side of the ceramic sensing element. The lower end of the lower bushing has a bottom with a center hole with the selective membrane attached. The lower free end of the selective membrane is tightly closed with a plug; the cavity limited by the inner surface of the lower bushing, the external part of the bottom of the ceramic sensing element and the inner surfaces of the selective membrane and the plug is leak-tight. The detector is additionally provided with an upper bushing and glass-ceramic sealant. The technical result is the enhanced service life and reliability of the hydrogen detector operation in a wide range of working medium parameters by providing leak-tightness of the inner cavity of the ceramic sensing element. 4 dependent claims, 1 figure.
摘要:
The patent discloses method and control system for gas injection into the coolant of a nuclear reactor plant. The method includes the following steps: gas to be injected into the coolant is supplied from the gas system to the above-coolant space; gas is injected into the gas system from the above-coolant space. Technical result: prevention of reuse of contaminated gas.
摘要:
Disclosed is a hydrogen igniter for igniting hydrogen contained in a gaseous medium, said hydrogen igniter comprising a housing with openings for the supply and discharge of a gaseous medium, and a filler in the form of bismuth oxide and/or lead oxide, disposed inside the housing. Also disclosed are a system for purifying a gaseous medium of hydrogen having such a hydrogen igniter, and a method for the repeated use of such a system. The igniter and the system can be used in a nuclear reactor facility
摘要:
The method and system for control of oxygen concentration in the coolant of a reactor plant including a reactor, coolant in the reactor, gas system, mass-exchange apparatus, disperser and an oxygen sensor in the coolant have been disclosed. The method includes the following steps implemented by the system: estimation of the oxygen concentration; comparison of the oxygen concentration with the permissible value; if the oxygen concentration is reduced, comparison of the reduction value and\or rate with the corresponding threshold value; if the reduction value and\or rate of oxygen concentration is below the threshold value, activation of the mass-exchange apparatus; if the reduction value and/or rate of oxygen concentration is above the corresponding threshold value, supply of oxygen-containing gas from the gas system to the near-coolant space and/or activation of the disperser. Technical result: improvement of controllability of oxygen concentration in coolant, enhancement of safety and extension of reactor plant operating life.