摘要:
Securing a location for safely burying and disposing of high-level radioactive waste produced in a nuclear reactor in a deep stable geological layer so that living environments are not significantly affected is difficult. 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), which is an area for using fast neutrons, and a second container (12), which is an area for using thermal neutrons in the nuclear reactor, 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.
摘要:
A nuclear fuel assembly component such as a control rod that has a cylindrical insert such as neutron absorbing material that is closely received within a cladding that is sealed at either end with end caps. The cylindrical member has grooves formed in its side wall extending from an upper surface to a lower surface to permit air to escape from the cladding as the cylindrical member is loaded into the cladding during manufacture.
摘要:
Disclosed are a fuel rod (300, 400) and a fuel bundle using the fuel rod (300, 400). The fuel rod (300, 400) may include first enriched uranium in a boost zone (310, 410) of the fuel rod (300, 400), wherein the boost zone (310, 410) may be arranged directly at a bottom of the fuel rod (300, 400). The fuel rod (300, 400) may also include second enriched uranium in a second zone (320, 420) of the fuel rod (300, 400), wherein the second zone (320, 420) is arranged over the boost zone (310, 410). The fuel rod (300, 400) may also include natural uranium in a third zone (330, 430) of the fuel rod, wherein the third zone (330, 430) is arranged over the second zone (320, 420). In this fuel rod(300, 400), a percent of enrichment of the enriched uranium in the boost zone (310, 410) is at least one percent.
摘要:
A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxide containing not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
摘要:
The invention relates to the field of atomic energy, more specifically to designs for working cassettes for reactors of the VVER-440 type. The cassette contains interconnected supporting corner members and a tail part and a head part with a framework situated therebetween, which comprises spacer grids made up of cells that are arranged according to a triangular mesh so as to form coaxial hexagonal rows about the centre of the grid. In the second or third or fourth row from the centre or in the corners of the third and fourth rows from the centre or in the corners of the third and second rows from the centre or in the corners of the fourth and second rows from the centre or in the middle of the fourth and second rows from the centre there are framework tubes which are connected to the tail part and are rigidly connected to the adjacent cells. This results in an increase in the rigidity and strength of the working cassette, an increase in safety under both normal and emergency operating conditions, more efficient use of fuel as a result of an improved water to uranium ratio and the possibility of spectrally controlling reactivity, and an increase in fuel cycle length and burn-up.
摘要:
A fuel element for a pressurized water reactor contains a multitude of fuel rods, which are guided inside a number of axially interspaced spacers (4) that, together, form a square grid having a multitude of holes (6) arranged in rows (10) and columns (8). A supporting tube is passed through a number of these holes and is joined with material fit inside said holes to the spacer (4) that does not contain any fuel. According to the invention, the supporting tubes are spread out in positions (Pa, Pb, Pc) within the grid in such a manner that, with a predetermined number of supporting tubes and a distribution thereof within the grid, which is rotationally symmetric around 90° with regard to a rotation about the central axis of the spacer (4), said central axis being perpendicular to the grid plane, the number of rows (10f) and columns (8f) that do not contain any supporting tubes is minimal. In addition, it is ensured that optionally remaining inner lying rows (10f) and columns (8f) that do not contain any supporting tubes are not situated next to one another.