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: 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: 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: An apparatus (100) for cleaning contact lenses is disclosed. The apparatus comprises a housing (110) having first (112) and second (114) housing sections which are joinable to form a chamber for receiving the lens. Each of the housing sections has an operative face (118, 120, 124, 126) facing the chamber formed for receiving the lens. A reactive layer (122) is provided on a portion of each operative face and the operative faces and the reactive layers are dimensioned and arranged whereby the reactive layers come into engagement with respective surfaces of a lens (155) positioned therebetween when the first and second housing sections are joined together. A portion of at least one of the operative faces is recessed relative to the other operative face to define an open volume within the chamber when the first and second housing sections are joined together. The first and second housing sections can be constructed to be in fluid communication when the apparatus is in an opened position.

Abstract: The present invention relates to a granular carrier and a method for producing the same, and to an apparatus for treating sewage or waste water by using the granular carriers. The granular carrier comprises a tire powder of 100 parts by weight, an EVA or its derivative of 30 to 50 parts by weight, and an activated carbon or inorganic micropowder equivalent thereto of 5 to 15 parts by weight. The granular carriers producing method comprises the steps of: mixing a tire powder of 100 parts by weight and an EVA or resin of 30 to 50 parts by weight, resolving the EVA or its derivative of the mixture at a temperature of 100 to 250° C., bonding an activated carbon to the tire powder, extruding the mixture, cutting the mixture extruded, and attaching the activated carbon powder to the EVA or its derivative dissolved on the surface of the cut part of the mixture. The sewage or waste water treatment apparatus is also disclosed.

Abstract: The present invention relates to a granular carrier and a method for producing the same, and to an apparatus for treating sewage or waste water by using the granular carriers. The granular carrier comprises a tire powder of 100 parts by weight, an EVA or its derivative of 30 to 50 parts by weight, and an activated carbon or inorganic micropowder equivalent thereto of 5 to 15 parts by weight. The granular carriers producing method comprises the steps of: mixing a tire powder of 100 parts by weight and an EVA or resin of 30 to 50 parts by weight, resolving the EVA or its derivative of the mixture at a temperature of 100 to 250.degree. C., bonding an activated carbon to the tire powder, extruding the mixture, cutting the mixture extruded, and attaching the activated carbon powder to the EVA or its derivative dissolved on the surface of the cut part of the mixture. The sewage or waste water treatment apparatus is also disclosed.

Abstract: A five or six gallon blow molded plastic water bottle has a regular hexagonal cross-section. The bottle is preferably made of polycarbonate and has a wall thickness of between 0.040 and 0.060 inch. An integral protrusion is formed on one face of the bottle and a depression is formed in a second diametrically opposite face of the bottle. Adjacent bottles may be stacked by inserting the protrusion of one bottle into the depression of an adjacent bottle. With the protrusion and depression of adjacent bottles engaged, the adjacent faces of each bottle contact each other so that the weight of the upper bottle which is borne by the lower bottle is distributed across the face. When the protrusion and depression of adjacent bottles are engaged, the top surface of the protrusion does not engage the bottom surface of the depression, so that indica labels or the like attached to the depression are not defaced or damaged.