摘要:
Various embodiments of a transportable nuclear power generator having a plurality of subcritical power modules are disclosed. Each of the plurality of subcritical power modules includes a fuel cartridge, a power conversion unit, and a housing substantially enclosing the fuel cartridge and the power conversion unit. The fuel cartridge contains a nuclear fuel and has a proximal end and a distal end. The power conversion unit includes a compressor turbine disposed at the proximal end of the fuel cartridge and a power turbine disposed at the distal end of the fuel cartridge. At least one of the plurality of subcritical power modules is movable with respect to the other of the plurality of subcritical power modules between a first position and a second position to control criticality of the nuclear fuel contained in the fuel cartridges of the plurality of subcritical power modules.
摘要:
A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped
摘要:
A thermal neutron shield comprising concrete with a high percentage of the element Boron. The concrete is least 54% Boron by weight which maximizes the effectiveness of the shielding against thermal neutrons. The accompanying method discloses the manufacture of Boron loaded concrete which includes enriching the concrete mixture with varying grit sizes of Boron Carbide.
摘要:
A nuclear fission reactor device including a core having an array of fissile material and which is capable of being transported to and from the place of operation using conventional transportation vehicles. In a first embodiment, the fissile material is a uranium hydride enriched 15%-to-20% with U-235. In a second embodiment, the fissile material is a uranium oxide enriched to 18% to 20% with U-235.
摘要:
A frame 10 with downwardly projecting members 52 mounts by means of a pair of hoists 36 and lifting bracket 42 downwardly into upwardly open recesses of complementary mounting members 54 secured to reactor head lifting legs 30. Frame 10 is mounted on the head either with lead wool shielding blankets 40 hanging from it or without. In the latter case, hangers 60 with blankets 40 hanging therefrom and horizontally gravity biased hooks 64 mounted on a curved beam 62, are lowered by hoist 36 until hooks 64 grapple, pivot and hang hanger 60 and the shielding on frame 10 at a location radially inwardly of the head bolt locations 22. The hook of hoist 36 is lowered until it is disengaged from the radially outwardly biased bail 70 of hanger 60.
摘要:
A nuclear reactor metal pressure vessel is surrounded by a concrete wall forming an annular space around the vessel. Thermal insulation is in this space and surrounds the vessel, and a coolant-conductive layer is also in this space surrounding the thermal insulation, coolant forced through this layer reducing the thermal stress on the concrete wall. The coolant-conductive layer is formed by concrete blocks laid together and having coolant passages, these blocks being small enough individually to permit them to be cast from concrete at the reactor installation, the thermal insulation being formed by much larger sheet-metal clad concrete segments. Mortar is injected between the interfaces of the coolant-conductive layer and concrete wall and the interfaces between the fluid-conductive layer and the insulation, a layer of slippery sheet material being interposed between the insulation and the mortar. When the pressure vessel is thermally expanded by reactor operation, the annular space between it and the concrete wall is completely filled by these components so that zero-excursion rupture safeguard is provided for the vessel.
摘要:
A multipurpose compartmented reactor building in which water fillable tankage dispersed about the pressure vessel and the containment vessel of a nuclear reactor provide primary shielding of a primary pressure boundary secondary shielding in the containment vessel therefor as well as protection against missiles from within and/or without the building; the tankage further providing multiple and immediate sources of water for emergency cooling and for flooding the containment boundary around the pressure vessels in the event of vessel rupture to keep the reactor core submerged; the tankage and water therein serving to absorb the energy release generated in a nuclear accident; such tankage when empty rendering the building light enough to be flatable as a hull for transport from a place of the construction to mooring at a site of ultimate use where the water sustaining the hull serves as a seismic damper to the hull in the event of an earthquake.
摘要:
A NUCLEAR-REACTOR STRUCTURE IN WHICH THE REACTOR CORE IS HOUSED IN A METALLIC ENCLOSURE SERVING IN PART AS A PRESSURE VESSEL AND AT LEAST IN PART AS A RADIOACTIVE SHIELD. THE WALLS OF THE STRUCTURE ARE MADE UP OF PRESTRESSED CAST-IRON BODIES WHICH MAY HAVE INTERFITTING OR INTERLOCKING FORMATIONS WITH ANY GAPS FILLED BY PRESSURE-RETAINING COMPOUNDS. STRESSING MAY BE EFFECTED BY RRODS OR CABLES RUNNING THROUGH THE CAST-IRON ELEMENTS OR BY EXTERNALLY POSITIONED CABLES, WIRES, BANDS OR RINGS.