摘要:
A getter element includes a getter material reactive with a fission product contained within a stream of liquid and/or gas exiting a fuel assembly of a nuclear reactor. At least one transmission pathway passes through the getter element that is sufficiently sized to maintain a flow of the input stream through the getter element at above a selected flow level. At least one transmission pathway includes a reaction surface area sufficient to uptake a pre-identified quantity of the fission product.
摘要:
This invention relates to a method of preparing a nuclear fuel including the step of depositing a coating which includes fluorine, or at least one compound thereof, around a kernel (12) of fissile material. The invention extends to a coated nuclear fuel particle (10).
摘要:
A fuel assembly for a boiling water reactor comprises a bottom tie plate, a top tie plate, and a first and a second group of vertical fuel rods, each including a column of fuel pellets surrounded by a cladding tube. The second group of fuel rods has a shorter active length than the first group of fuel rods. Both the first and the second group of fuel rods extend between the bottom tie plate and the top tie plate. The second group of fuel rods comprises a fission gas plenum surrounded by a plenum tube arranged above the cladding tube. The main part of the plenum tube has a cross-section area which is smaller than the cross-section area of the cladding tube.
摘要:
An agent for trapping the radioactivity of the fission products which appear in a nuclear fuel based on sintered uraniferous oxides in the course of irradiation characterized in that it comprises a stable oxygenated compound, a combination of at least two metallic oxides and at least one oxide of a non-radioactive isotope of the radioactive fission product or products whose radioactivity is to be trapped.
摘要:
A nuclear fuel element comprising sintered pellets based on uraniferous oxide which are surrounded by a metallic sheath and permitting trapping of the fission products which appear in the course of irradiation characterized in that the pellets contain or are coated with or that the sheath is internally coated with an agent for trapping said fission products based on mixed metallic oxide comprising SiO.sub.2 and one at least of the oxides ZrO.sub.2 or CeO.sub.2.
摘要:
A fuel bundle is disclosed in which interspersed part length fuel rods define between the end of the fuel rods and the upper tie plate void regions which are not otherwise occupied. Full length fuel rods adjacent to these regions are provided with an expanded upper plenum region which effectively increases the fuel rod diameter at the end of the upper two phase region of the fuel bundle. Under normal circumstances and a fuel bundle with only full length fuel rods, such an expansion of the upper regions of the fuel rods would cause unacceptable pressure drop. Where such expansion occurs adjacent the vacated volumes created by the part length fuel rods, unacceptable pressure drop does not occur. Consequently, and with the expanded plenum volume, a longer length of active fuel pellets can be accommodated within the full length fuel rods.
摘要:
A hydride blister-resistant nuclear fuel rod cladding has a tubular cladding formed from a zirconium-based alloy which has a thin nickel base film, of a thickness of about 0.01 to 5 microns distributed over between 1-40 percent of the area of the internal surface of the tubular cladding. The dispersed nickel base film provides multiple sites for hydride transport from the interior of the nuclear fuel rod and prevents localized hydride transport and resulting hydride blistering.
摘要:
A nuclear reactor component such as a fuel rod, burnable absorber rod, or neutron absorber rod, comprising a hermetically sealed metallic tube containing a solid material such as a nuclear fuel, burnable absorber, or neutron absorber, within a helium atmosphere, which solid material will release tritium into the helium atmosphere, has added thereto about 2-3 percent by volume of a gas, selected from oxygen, carbon monoxide and carbon dioxide. The addition of this gas to the helium atmosphere is effective to form an oxide layer on the inner surface of the metallic tube and significantly reduce the permeation of tritium through the metallic tube, such that the tritium is retained within the reactor component.
摘要:
A nuclear fuel element suitable for use in fast breeder. The fuel element has a clad tube and a wire spacer wound round the clad tube. The clad tube of the fuel element is composed of a first clad tube and a second clad tube which are connected to each other through an intermediate plug. The first clad tube extends upwardly from the intermediate plug. The upper end of the first clad tube is closed by an upper end plug, while the lower end of the second clad tube is closed by a lower end plug. The first clad tube is charged with a multiplicity of fuel pellets, while the second clad tube defines a gas plenum therein. The spaces inside the first and second clad tubes are communicated with each other through vent holes formed in the intermediate plug. The wire spacer is wound round the first clad tube and is fixed at its one end to the end plug attached to the first clad tube and at its other end to the intermediate plug.
摘要:
A method of manufacturing a nuclear fuel element which contains a pre-activated non-evaporable getter material such that the getter material starts to sorb gas at a temperature lower than the temperature at which the fuel element walls start to sorb gas which getter action at least partially takes place at subatmospheric pressure.