Class / Patent application number | Description | Number of patent applications / Date published |
376246000 | Flowmeters | 7 |
20090257544 | Methods and Devices Relating to a Nuclear Light Water Reactor of the Boiling Water Kind - A method of determining the R-factor for a bundle of nuclear fuel rods in a nuclear light water reactor of the boiling water reactor kind. The R-factor is a factor that accounts for the weighted local power influence on a fuel rod. A local R-factor (R | 10-15-2009 |
20100226469 | ATOMIC REACTOR WATER SUPPLY PIPING STRUCTURE AND ULTRASONIC FLOWMETER SYSTEM - A technology for accurately measuring with the use of an ultrasonic flowmeter the flow rate through a nuclear reactor water supply piping interposed between a nuclear reactor and a nuclear reactor water supply pump. In a reactor coolant cleaning system ( | 09-09-2010 |
20130235965 | Apparatus For Testing Loss-Of-Coolant Accident Using Model Of Nuclear Containment Building - Provided is an apparatus for testing a loss-of-coolant accident using a model of a nuclear containment building, including a containment vessel of which an upper surface is opened and side and lower surfaces are transparent; an internal structure which is disposed in the containment vessel; a hose pipe which is disposed at an upper side of the containment vessel; and a measuring device which is disposed at the lower surface of the containment vessel so as to monitor movement of fluid and debris in the containment vessel. | 09-12-2013 |
20140072085 | METHOD AND SYSTEM FOR A SPENT FUEL POOL LEVEL MEASUREMENT WITHOUT ELECTRICAL POWER - A method and apparatus for measuring a liquid level of a Spent Fuel Pool of a Light Water Reactor without using electrical power. The method and apparatus may use a pressurized gas source connected to tubing or piping that may discharge near the bottom of the Spent Fuel Pool. The system may include a flow meter and throttle valve that may be used to determine a required gas pressure to provide a specified flow rate of gas for known Spent Fuel Pool water levels. By obtaining calibration data points of pressure and flow for multiple Spent Fuel Pool water levels, a calibration curve may be obtained that allows for the measurement of Spent Fuel Pool liquid level using the system, without the need for electrical power. | 03-13-2014 |
20140185727 | POWER MONITORING SYSTEM FOR A NUCLEAR REACTOR - According to an embodiment, a power monitoring system for a nuclear reactor comprises at least a first system and second system. The first system and the second system respectively comprise a plurality of APRM units, a plurality of FLOW units, and a plurality of OPRM units. The APRM units respectively generate an LPRM signal that indicates the local output of neutrons by the reactor core, and generate an APRM signal indicating the average output of the reactor core, based on the LPRM signal. The FLOW units respectively generate a FLOW signal indicating the flow rate of reactor coolant. The OPRM units respectively are supplied with the LPRM signal and the APRM signal from at least two aforementioned APRM units and are supplied with the FLOW signal from at least one aforementioned FLOW unit; and, based on the supplied LPRM signals, APRM signals and FLOW signals, generate a trip signal for shutting down the reactor. | 07-03-2014 |
20150063519 | Method for Measuring Primary Coolant Flow in a Fluoride Salt Cooled High Temperature Reactor - This invention relates to the field of coolant flow in a fluoride salt cooled high temperature reactor. In particular, the invention relates to the discovery of use of nitrogen-16 and/or fluoride-20 decay signature to measure coolant flow. The method of the invention comprises detecting gamma radiation emanating from nitrogen-16 activity and/or fluorine-20 activity within the reactor coolant at a first position along the reactor coolant loop; detecting the gamma radiation emanating from the nitrogen-16 activity and/or fluorine-20 activity within the reactor coolant at a second position along the reactor coolant loop downstream of said first position. The gamma radiation detected from the first position and second position are then cross-correlated, thereby determining the transit time of corresponding gamma activity perturbations viewed at the two detector locations. | 03-05-2015 |
20150098544 | Sustainable Modular Transmutation Reactor - A light water reactor to safely convert depleted uranium into a fuel source that could be used as a sustainable source of energy for centuries. The reactor is a type of breed-burn reactor uniquely combined with a proliferation-resistant fuel cycle with no uranium enrichment and no plutonium isolation. It is comprised of a compact factory-produced fast region and a thermal region that produces about 95% of the core power and contains the passageways for transports of delayed-neutron emitters to the fast region, where they can provide additional neutrons (source-based mode) or all the necessary excitation without an external neutron source (self-regulating mode). A second embodiment of the invention is a small unit driven by a neutron source with beam recycling for propulsion, electrical power or radioisotope production. It could also serve as a demonstration facility for the transmutation reactor with fission-fusion fuel. | 04-09-2015 |