Class / Patent application number | Description | Number of patent applications / Date published |
376250000 | Leak detection | 9 |
20080292041 | Method and system for early sensing of water leakage, through chemical concentration monitoring, in nuclear reactor system using liquid metal and molten salt - A method of early sensing of water leakage, through chemical concentration monitoring, in a nuclear reactor system using a liquid metal and molten salt, the method including: measuring an electrical conductivity and a mass spectrum of a first channel and a second channel of a heat-related device included in the nuclear reactor system using the liquid metal and the molten salt; calculating a first identification value associated with the water leakage in the heat-related device using the measured electrical conductivity; calculating a second identification value associated with the water leakage in the heat-related device using the measured mass spectrum; and sensing the water leakage by comparing a predetermined reference value and a summed identification value, the summed identification value being the sum of the first identification value and the second identification value. | 11-27-2008 |
20100239061 | REACTOR CONTAINMENT VESSEL AND WATER LEAK DETECTION FLOOR - A water leak detection floor transversally suspended by a pedestal side wall is installed between a reactor pressure vessel and a molten core holding apparatus. If a water leak occurs at the reactor pressure vessel, the water leak detection floor receives and detects the leak water. In a core meltdown accident, corium melts and penetrates the water leak detection floor and deposits on the molten core holding apparatus. | 09-23-2010 |
20110058636 | METHOD OF AND AN APPARATUS FOR MONITORING THE OPERATION OF A NUCLEAR REACTOR - The invention concerns a method of monitoring the operation of a reactor of a nuclear plant. The reactor is operated at a given total reactor power during a normal fuel operation cycle. The radioactivity level in the off-gas stream is continuously measured to detect a possible release of fission gases from the fuel rods as a consequence of a fuel leakage due to a defect on the cladding of any of the fuel rods in any of the fuel assemblies. An instantaneous power distribution is regularly established in the core and a power distribution pattern over time is established based on the instantaneous power distributions. The release of fission gases and the established power distribution pattern are then combined and correlations between changes in the release of fission gases and in the power distribution pattern are observed in order to determine a position of the defect. | 03-10-2011 |
20110164715 | SYSTEM AND METHOD FOR DETECTING LEAKAGE OF NUCLEAR REACTOR COOLANT USING LASER INDUCED EMISSION SPECTRUM - System and method for detecting and/or predicting in a field the leakage of nuclear reactor coolant that may occur at the pressure boundary of the primary system of a nuclear reactor. The system and method for detecting the leakage of nuclear reactor coolant uses a laser induced emission spectrum. The leakage of coolant is detected by detecting boron (B), a main component of the coolant, in corrosive products generated at the nuclear reactor pressure boundary on the basis of laser spectroscopy. An embodiment of the system for detecting leakage of nuclear reactor coolant may include a laser generator, a laser focusing lens, an emission collector, and emission spectrum analyzer. | 07-07-2011 |
376251000 | Fuel element leak detection | 5 |
20100040186 | FUEL ROD INTERNAL PRESSURE MEASUREMENT - A method for determining a leaking nuclear fuel rod that remotely measures the internal pressure in the plenum region of the fuel rod by remotely measuring the thermal response of the rod when a localized heating is imposed on the outside of the rod in the plenum region. The temperature of the cladding at two symmetrically spaced points on either side of the location where the heating is imposed is remotely monitored as a function of time and compared to a standard to determine the internal pressure of the plenum. | 02-18-2010 |
20110243293 | Systems and Methods for Servicing a Fuel Assembly in a Light Water Reactor - Systems and methods for servicing a fuel assembly in a light water reactor include those for controlling flow through a fuel assembly to maintain debris in the fuel assembly during removal and transportation of the fuel assembly, those for discharging debris from the fuel assembly, and those for isolating and sampling the water chemistry of a fuel assembly. An exemplary system includes a closure device configured to seal a mast to a fuel assembly to surround the upper opening of the fuel assembly and provide a flow control channel between a void in the mast and a lower opening in a lower tie plate. | 10-06-2011 |
20140192943 | FUEL ROD TESTING APPARATUS FOR NUCLEAR FUEL ASSEMBLY - Disclosed is a fuel rod testing apparatus for a nuclear fuel assembly. The fuel rod testing apparatus includes a helium leakage testing chamber having a gate so that a fuel rod is horizontally loaded/unloaded and testing whether or not helium leaks from the fuel rod, a fuel rod upward/downward transfer unit that has first and second transfer sections located in front of the gate and horizontally installed apart from each other in order to guide the fuel rod loaded into or unloaded from the helium leakage testing chamber, and that vertically drives the first and second transfer sections, and a main frame that has a upper transfer section disposed in parallel in a lengthwise direction of the fuel rod upward/downward transfer unit and having an inclined face and a lower transfer section installed at a lower portion of the upper transfer section and having an inclined face. | 07-10-2014 |
20140205049 | SYSTEMS AND METHODS FOR DETECTING A LEAKING FUEL CHANNEL IN A NUCLEAR REACTOR - Methods and systems for detecting an individual leaking fuel channel included in a reactor. One system includes a plurality of inlet lines and a plurality of outlet lines. Each of the plurality of inlet lines feeding annulus fluid in parallel to an annulus space of each of a first plurality of fuel channels included in the reactor, and each of the plurality of outlet lines collecting in parallel annulus fluid exiting an annulus space of each of a second plurality of fuel channels included in the reactor. In some embodiments, the system also includes a detector positioned at an outlet of each of the plurality of outlet lines configured to detect moisture in annulus fluid and identify a first position of an individual leaking fuel channel, and an isolation valve positioned at an inlet of each of the plurality of inlet lines operable to stop annulus fluid from circulating through one of the plurality of inlet lines and to identify a second position of the individual leaking fuel channel. | 07-24-2014 |
376253000 | By the detection of fission products external to the fuel element | 1 |
20110051876 | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system - Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system. | 03-03-2011 |