摘要:
The present invention relates to the field of fused-salt nuclear reactors and its object is the extraction of the gases produced in the course of operation of these reactors.The process according to the invention consists in placing into position a piece of material permeable for gases and impermeable for the used fused salts, for instance, a piece of graphite, in such a way that part of the surface of this piece is in contact with the circuit of the radioactive salts and another part connected to a gas suction device.The piece could also be scavenged in its mass by a flow of inert gas.Application is contemplated in reactors using a mixture of lithium fluoride, beryllium fluoride, and uranium and/or thorium fluoride.
摘要:
A novel system and method of operating a fluid fuel nuclear reactor is provided in which heat for power generation is transferred directly from the fluid fuel to a purge material while the purge material simultaneously sweeps neutron-absorbing fission products from the fluid fuel.
摘要:
972,044. Cold separation of gas mixtures. GES. FUR LINDE'S EISMASCHINEN A.G. June 26, 1963 [July 4, 1962], No. 25375/63. Heading F4P. [Also in Division G6] Reduction of the content of low boiling trace impurities e.g. carbon monoxide, methane, nitrogen, oxygen and rare gases found in carbon dioxide is effected in a rectification column 17 to which feed gas is admitted through an expansion nozzle 16, pure liquid carbon dioxide is withdrawn from the base through a duct 21 and impurity-rich carbon dioxide effluent gas is withdrawn from the head through a duct 30 and said effluent is condensed in part in an exchanger 26 and returned through a duct 31 to serve as reflux whilst the uncondensed effluent gas is used to cool incoming feed gas in an exchanger (not shown). In operation compressed crude carbon dioxide having been cooled in exchangers 12; 13 is expanded into a chamber 14, liquefied in an exchanger 15 cooled by liquid carbon dioxide in duct 21, and a portion thereof expanded at nozzle 16 whilst the remainder is expanded at a value 19 into a separating chamber 20 into which is also expanded at a valve 24 pure liquid carbon dioxide from the exchanger 15 at a valve 34 crude liquid carbon dioxide from chamber 14. The liquid carbon dioxide from chamber 20 is vaporized in exchanger 26, added to vapour from chamber 20 and is forced by a compressor 28 into a duct 29 leading to a nuclear reactor, Fig. 1 (not shown), to serve as coolant. Contaminated effluent is vented to atmosphere through a duct 32.
摘要:
A fuel assembly for a nuclear water reactor having an upstream end, a downstream end, and a flow interspace between the upstream and downstream ends. Fuel rods are provided in the flow interspace between the upstream and downstream ends. The flow interspace permits a flow of coolant through the fuel assembly along a flow direction from the upstream end to the downstream end. A filter device is provided to catch debris particles in the flow of coolant. The filter device has a first filter zone for a major part of the flow of coolant, and a second filter zone for a minor part of the flow of coolant. The first filter zone has a first filtering efficiency and the second filter zone has a second filtering efficiency. The second filtering efficiency is higher than the first filtering efficiency.
摘要:
A base portion for use in a bottom nozzle of a fuel assembly in a nuclear reactor includes a top surface, a bottom surface, and a plurality of vertical wall portions arranged in a generally squared grid-like pattern which extend between the bottom surface and the top surface and which define a plurality of non-circular passages passing between the bottom surface and the top surface through the base portion.
摘要:
A purification method for spent fuel pool water from nuclear power generation, the method comprising: passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus for the water comprising an ion exchange resin layer and a metal-doped resin layer which is laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer wherein the water to be treated is contacted with the metal-doped resin layer to decompose a pro-oxidant contained in the water; and subsequently contacting the water with the ion exchange resin.
摘要:
A method for purifying water in a spent fuel pool in a nuclear power plant, the method including passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus. The apparatus includes an ion exchange resin layer and a metal-doped resin layer laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer. The method includes contacting the water with the metal-doped resin layer to decompose a pro-oxidant contained in the water and subsequently contacting the water with the ion exchange resin to produce purified water.
摘要:
A coating of niobium oxide, zirconium titanate, or nickel titanate is formed on at least a part of a surface of a jet pump member constituting a jet pump serving as a reactor internal structure of a boiling water reactor. Further, a solution containing, e.g., a niobium compound is applied to at least a part of the surface of the jet pump member constituting the jet pump, and the jet pump member coated with the solution is heat-treated to form a coating of, e.g., niobium oxide. With this configuration, the jet pump member constituting the jet pump of the boiling water reactor is provided such that deposition of crud can be sufficiently suppressed on the jet pump member.