Abstract: Provided is a nuclear reactor having a load following control system in which a nuclear reaction therein is naturally controlled by the generated heat, the nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a-liquid or a gas having a thermal expansion coefficient greater than that of the neutron reflector, and converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.

Abstract: A nuclear power generation system being safe and easily controlled by load following. The nuclear power generation system has a nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core having metallic fuel containing at least one selected from uranium-235, uranium-238 and plutonium-239; a reactor vessel containing the reactor core; metallic sodium loaded into the reactor vessel and heated by the reactor core; and a neutron reflector for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the reactor core being maintained at or above about 1. The neutron reflector is coupled to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector.

Abstract: Engineering safety systems always have insufficiencies in terms of safety, and construction of a complete safety system causes installation costs for the safety system to become very high.

Abstract: A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.

Abstract: Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.

Abstract: Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.

Abstract: A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.

Abstract: A method for producing oxidized water for sterilization use which contains chlorine dioxide, said method comprising: electrolyzing tap water containing chlorine ions using a three-chamber-type electrolysis vessel, in which an intermediate chamber is located between an anode chamber and a cathode chamber; trapping the chlorine ions dissolved in the tap water; and electrolytically oxidizing the trapped chlorine ions on an anode electrode. A partitioning membrane that isolates the anode chamber from the intermediate chamber is composed of a fluorine-containing cation exchange membrane and an anion exchange membrane, wherein a porous anode electrode is adhered onto the fluorine-containing cation exchange membrane in the partitioning membrane.

Abstract: The present invention provides a small nuclear power generation system being safe and easily controlled by load following, and allowing reductions in manufacturing costs and maintenance and management costs. The small nuclear power generation system has a small nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core 4 having metallic fuel containing one or both of uranium (235, 238) and plutonium-239; a reactor vessel 1 containing the fuel assembly reactor core 4; metallic sodium loaded into the reactor vessel 1 and heated by the fuel assembly reactor core 4; and a neutron reflector 2 for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the fuel assembly reactor core 4 being maintained at or above about 1.

Abstract: A compact nuclear power generation system includes a reactor (3) comprising a core (2) which uses metal fuel containing either or both of uranium-235/238 and plutonium-239. A reactor vessel (1) houses the core (2). Metal sodium primary coolant (8) is heated by the core (2). A neutron reflector (9) maintains the effective multiplication factor of neutrons emitted from the core (2) at approximately one or more to bring the core into a critical state. The neutron reflector is movable from a lower part towards an upper part of the core. The heated metal sodium is supplied to a main heat exchanger (15) which is located outside the reactor. A secondary coolant of supercritical carbon dioxide, which circulates through the main heat exchanger, is in heat exchange with the heated metal sodium. The heated secondary coolant drives a turbine (20). A power generator (21) can be operated by the driven turbine.

Abstract: A method for producing oxidized water for sterilization use which contains chlorine dioxide, said method comprising: electrolyzing tap water containing chlorine ions using a three-chamber-type electrolysis vessel, in which an intermediate chamber is located between an anode chamber and a cathode chamber; trapping the chlorine ions dissolved in the tap water; and electrolytically oxidizing the trapped chlorine ions on an anode electrode. A partitioning membrane that isolates the anode chamber from the intermediate chamber is composed of a fluorine-containing cation exchange membrane and an anion exchange membrane, wherein a porous anode electrode is adhered onto the fluorine-containing cation exchange membrane in the partitioning membrane.

Abstract: [Problem] To build a secure and high-efficiency power generation system while achieving a further reduction in the size of the entire system. [Solution] A compact nuclear power generation system is provided with a reactor (3) comprising a core (2) which uses metal fuel containing either or both of uranium-235/238 and plutonium-239, a reactor vessel (1) which houses the core (2), metal sodium which is filled into the reactor vessel (1) and heated by the core (2), and a neutron reflector (9) which maintains the effective multiplication factor of neutrons emitted from the core (2) at approximately one or more to bring the core into a critical state. A main heat exchanger (15) is installed outside the reactor (3). The metal sodium heated by the reactor (3) is supplied to the main heat exchanger (15), and supercritical carbon dioxide that is subjected to heat exchange with the heated metal sodium circulates therethrough.

Abstract: A method for activating hydrogen molecules dissolved in water and stabilizing the concentration of the hydrogen molecules is provided. The method for activating and stabilizing hydrogen molecules dissolved in water is characterized by allowing hydrogen ions to coexist with the hydrogen molecules.

Abstract: An apparatus for producing in the home hydrogen-dissolved drinking water that is suitable for drinking, has a high dissolved hydrogen concentration, and a long dissolved hydrogen life. A hydrogen-dissolved drinking water production apparatus includes an electrolytic cell through which water can pass for producing drinking water having a pH in a range of 2.5 to 8.5, and in particular, in a range of 5.8 to 8.5, and a dissolved hydrogen concentration of 0.1 ppm or more by supplying high-purity water having a conductivity of 50 ?S/cm or less.

Abstract: A method and apparatus for electrolytically producing oxidation reduction potential water from aqueous salt solutions for use in disinfection, sterilization, decontamination, wound cleansing. The apparatus includes an electrolysis unit having a three-compartment cell (22) comprising a cathode chamber (18), an anode chamber (16), and a saline solution chamber (20) interposed between the anode and cathode chambers. Two communicating (24, 26) membranes separate the three chambers. The center chamber includes a fluid flow inlet (21a) and outlet (21b) and contains insulative material that ensures direct voltage potential does not travel through the chamber. A supply of water flows through the cathode and anode chambers at the respective sides of the saline chamber. Saline solution flows through the center chamber, either by circulating a pre-prepared aqueous solution containing ionic species, or, alternatively, by circulating pure water or an aqueous solution of, e.g.

Abstract: An apparatus for producing in the home hydrogen-dissolved drinking water that is suitable for drinking, has a high dissolved hydrogen concentration, and a long dissolved hydrogen life. A hydrogen-dissolved drinking water production apparatus includes an electrolytic cell through which water can pass for producing drinking water having a pH in a range of 2.5 to 8.5, and in particular, in a range of 5.8 to 8.5, and a dissolved hydrogen concentration of 0.1 ppm or more by supplying high-purity water having a conductivity of 50 ?S/cm or less.

Abstract: This invention provides the oxidative mixed water with pH around 7.4 ranging from the weak acidity to weak alkalinity, high power of killing microorganisms, and high power of healing wound by electrolysis using the three-compartment cell composed of an anode compartment, a cathode compartment, and a middle compartment between the anode compartment and the cathode compartment. Mixing anode water with cathode water produced using the three-compartment device forms the oxidative mixed water.

Abstract: Provided is an aqueous solution in which hydrogen dissolved therein has a long life duration at low cost. Specifically disclosed is an aqueous solution having hydrogen dissolved therein at a concentration of not less than 0.01 ppm and not higher than the saturated concentration, wherein the aqueous solution contains a substance having a reducing aldehyde group and/or a glycoside hydroxyl group in an amount of 10 to 300000 ppm.

Abstract: A method for activating hydrogen molecules dissolved in water and stabilizing the concentration of the hydrogen molecules is provided. The method for activating and stabilizing hydrogen molecules dissolved in water is characterized by allowing hydrogen ions to coexist with the hydrogen molecules.

Abstract: The present invention provides an electrolytic cell, which can efficiently produce charged water having an excellent performance of improving surface cleaning or treatment of an object, e.g., semiconductor, glass, or resin and of cleaning and sterilizing medical device.