摘要:
The invention relates to a device for performing a leak test on a fuel rod capsule, which contains at least one fuel rod and test gas, which device comprises a test container, which is designed to accommodate at least one fuel rod capsule and can be lowered into a pool of a nuclear plant flooded with water. According to the invention, a mass spectrometer is fluidically connected to the interior of the test container in such a way that a gas flow can be fed to the mass spectrometer in order to sense the concentration of the test gas that has diffused into the test container from the fuel rod capsule.
摘要:
A method and system detects failures in nuclear fuel assemblies (600). A water treatment device degasses/removes fission gases from water used in the canister (500) of a vacuum sipping device (30). A sipping procedure then detects a failure in a fuel assembly in the canister. The degassing improves a signal-to-noise ratio of the detector used during the sipping process, and improves the failure detection sensitivity of the system. Additionally and/or alternatively, gas may be recirculated through the canister water before the vacuum is applied so that fission gas concentration in the recirculating gas reaches a baseline equilibrium with the canister water. The vacuum is thereafter applied and the sipping procedure proceeds such that an increase in detected radioactivity over the baseline equilibrium indicates a leak in the fuel assembly.
摘要:
Fuel rods of fuel assemblies of a boiling water reactor are tested for leaks. A plurality of fuel assemblies are each arranged adjacent to one another in a cell of the upper core grid of the boiling water reactor. A hood is placed above a plurality of cells A water sample is taken from each of the cells, and the water samples from a plurality of cells forming a group are combined and tested for the presence of radioactive fission products A plurality of groups are analyzed simultaneously in a number, which number corresponds to the number of groups, of measurement channels. Where a result of a group is positive, the cells of the group are tested separately by the measurement channels. Those fuel assemblies of a cell that is found positive are tested individually outside the hood.
摘要:
An electrolyte is circulated between the surface to be machined, raised to an anode potential, and a tool electrode (9') raised to a cathode potential. The electrolyte contains lithium nitrate as a unique active product with a concentration of between 20 g/l and 2350 g/l and preferably between 50 g/l and 250 g/l. The process can be applied to the machining of the surface of any metallic component and in particular to the machining of the internal surface of tubular components (5) such as penetrations in the vessel bottom or closure head of a nuclear reactor; in this case the electrochemical machining cell consists of a cylindrical tool electrode (9') placed inside the component to be machined.
摘要:
A process and system for the rapid concentration, separation and measurement of Kr-85 and Xe-133. By measuring the amount of Kr-85 radioisotope which is present, false positive signals for the vacuum sipping process can be eliminated. The fission gases are trapped by passing the recirculating gas stream through an adsorbing media. During this process, a known mixture of nonradioactive krypton and xenon is added to the gas stream which enters a thermal conductivity (TC) detector to calibrate the latter. The trapped gases are desorbed and injected into the inlet of a separating column. The column discharges into the TC detector. The TC detector discharge is diverted for counting to an evacuated beta detector chamber during the time that krypton is sensed by the TC detector. Any minute amount of Kr-85 is captured in the chamber, free of Xe-133. The detector discharge is diverted for counting to another evacuated beta detector chamber during the time that xenon is sensed by the TC detector. Any minute amount of Xe-133 is captured in the chamber, free of Kr-85.
摘要:
Nuclear fuel elements or slugs are removed from the nuclear reactor cores and subjected to inspection, according to the invention, by introducing a plurality of such elements into a submerged inspection vessel which is then closed, the liquid driven out by compressed air and deionized water (deionate) circulated through the inspection vessel at a constant rate. A portion of the deionized water is branched from the circulating stream at a constant rate and the activity of at least one fission-product nuclide is determined continuously to plot the activity versus temperature, thereby signaling a possible defect in the shell of a fuel element. In addition, ultrasonic vibration is applied in the inspection vessel to the fuel elements so that deposits on the exterior thereof are released into the deionate whose circulating path includes a filter and an ion-exchange column for removal of such deposits.
摘要:
An apparatus for detecting failure of the nuclear fuel rod has an outer cap and 16 (sixteen) inner caps. In checking for any faulty fuel rods, the outer cap is placed to cover the upper ends of 16 (sixteen) fuel assemblies mounted in the reactor core, while the inner caps in the outer cap are disposed on corresponding one of the fuel assemblies. To the outer cap are attached 4 (four) air supplying hoses. The inner caps receive corresponding one of 16 sampling tubes attached to the outer cap, and coolant sampling hoses are connected to the sampling tubes. A bundle member is fixed to the center of the upper surface of the outer cap. The four air supplying hoses and 16 coolant sampling hoses are fixed to the bundle member. The bundle member has a handle attached thereto.
摘要:
A method for simultaneously testing a plurality of fuel rod assemblies for leakage of radioactive gas, comprising the steps of removing the cover from a nuclear vessel containing the fuel rods, positioning a fixture over the fuel rods, reducing the hydrostatic pressure surrounding the fuel rods allowing gas to leak into the surrounding water, collecting water from about each fuel rod assembly in a separate chamber, separating gas from the water and testing the gas for the presence of radioactivity.
摘要:
This invention relates to a method for determining defective final layers of carbon on triso-coated fuel particles and the like. Samples of the particles are subjected to a high temperature treatment with gaseous chlorine and thereafter radiographed. The chlorine penetrates through any defective carbon layer and reacts with the underlying silicon carbide resulting in the volatilization of the silicon as SiCl.sub.4 leaving carbon as a porous layer. This porous carbon layer is easily detected by the radiography.