Patent ReferencesMethod and apparatus for protecting a nuclear reactor Nuclear reactor power control method and device Boiling water reactor stability control Enhanced transient overpower protection system Real-time analysis of power plant thermohydraulic phenomena Method for determining core flow rate and water temperature/density in boiling water reactor Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors Method for generating control system setpoints with implicit dependencies Methods of reactor system pressure control by reactor core power modulation Patent #: 6198786 InventorsApplicationNo. 09683335 filed on 12/14/2001US Classes:376/245, TESTING, SENSING, MEASURING, OR DETECTING A FISSION REACTOR CONDITION376/207, WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW)376/210, By coolant flow376/219, By movement of control element or by release of neutron absorbing material376/246, Flowmeters376/247Temperature or pressure measurementExaminersPrimary: Palabrica, RAttorney, Agent or FirmInternational ClassG21C 1700AbstractA computerized method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at core flows lower than normal operating parameters is provided. The operating domain is characterized by a map of the reactor thermal power and core flow. The computerized method includes determining by computer simulation a load line characteristic that is elevated over normal operating parameters and that increases reactor performance over normal operating parameters, performing safety evaluations by computer simulation at the elevated load line to determine compliance with safety design parameters, and performing operational evaluations by computer simulation at the elevated load line.Other References
| |