Patent classifications
G21D1/02
POWER CONVERSION SYSTEM FOR NUCLEAR POWER GENERATORS AND RELATED METHODS
A power conversion system for converting thermal energy from a heat source to electricity is provided. The system includes a chamber including an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The chamber also includes an outer shroud substantially surrounding the inner shroud. The chamber includes a source heat exchanger disposed in the internal passageway, the source heat exchanger being configured to receive a heat transmitting element associated with the heat source external to the chamber, and to transfer heat energy from the heat transmitting element to the working fluid. The system also includes a compressor disposed adjacent the inlet of the inner shroud and configured to transfer energy from the compressor to the working fluid, and an expander disposed adjacent the outlet of the inner shroud.
Scalable communication switch system
Systems, methods, apparatuses, and software for computing systems are provided herein. In one example, a system includes processing modules each having a communication interface and a processor, and additional modules each having a communication interface. Communication switch circuitry is coupled to the communication interfaces of the processing modules and the communication interfaces of the additional modules, wherein the communication switch circuitry is configured to establish isolation among ports in the communication switch circuitry for one or more processing modules and one or more additional modules. At least one processor instantiates access to the one or more additional modules for the one or more processing modules over at least the isolation.
Scalable communication switch system
Systems, methods, apparatuses, and software for computing systems are provided herein. In one example, a system includes processing modules each having a communication interface and a processor, and additional modules each having a communication interface. Communication switch circuitry is coupled to the communication interfaces of the processing modules and the communication interfaces of the additional modules, wherein the communication switch circuitry is configured to establish isolation among ports in the communication switch circuitry for one or more processing modules and one or more additional modules. At least one processor instantiates access to the one or more additional modules for the one or more processing modules over at least the isolation.
CARBON DIOXIDE CAPTURE
A system for capture of atmospheric carbon dioxide. The system includes a carbon dioxide capture device having a capture medium operable to capture atmospheric carbon dioxide under a first set of thermodynamic conditions, and to release carbon dioxide under a second set of thermodynamic conditions different to the first set of thermodynamic conditions. The first set of thermodynamic conditions includes a first temperature range and the second set of thermodynamic conditions includes a second temperature range. A heat engine is configured receive a working fluid at an inlet temperature and arranged to discharge at least a portion of the working fluid at a discharge temperature in the second temperature range or higher, and a heat transfer arrangement is configured to convey heat from discharged working fluid to the capture medium to release carbon dioxide therefrom.
Method and system for determining background water temperature of thermal discharge from operating nuclear power plants based on remote sensing
Disclosed are a method and a system for determining a background water temperature of thermal discharge from operating nuclear power plants based on the remote sensing. The system includes a station selection module, a model construction module, a background water temperature calculation module and a temperature rise calculation module; the general idea: constructing linear regression coefficients between water temperature reference station and water temperature estimation stations before the operation of the nuclear power plant based on historical satellite remote sensing water temperature data, and establishing a linear relationship model to calculate the background water temperature of the water temperature estimation of the operating nuclear power plant. The specific implementation route: the station selection module is connected with the model construction module, the model construction module is connected with the background water temperature calculation module, and the background water temperature calculation module is connected with the temperature rise calculation module.
Method and system for determining background water temperature of thermal discharge from operating nuclear power plants based on remote sensing
Disclosed are a method and a system for determining a background water temperature of thermal discharge from operating nuclear power plants based on the remote sensing. The system includes a station selection module, a model construction module, a background water temperature calculation module and a temperature rise calculation module; the general idea: constructing linear regression coefficients between water temperature reference station and water temperature estimation stations before the operation of the nuclear power plant based on historical satellite remote sensing water temperature data, and establishing a linear relationship model to calculate the background water temperature of the water temperature estimation of the operating nuclear power plant. The specific implementation route: the station selection module is connected with the model construction module, the model construction module is connected with the background water temperature calculation module, and the background water temperature calculation module is connected with the temperature rise calculation module.
Reactor Containment Vessel Vent System
A reactor containment vessel vent system continuously releases steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system, the noble gas filter that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter and the reactor containment vessel are connected to each other by the return pipe via the intermediate vessel. When the radioactive noble gases having pressure equal to or higher than predetermined pressure stay in the immediate upstream portion of the noble gas filter, the staying radioactive noble gases flows into the intermediate vessel by the relief valve. Thus, steam permeability is maintained and the system continuously releases the steam.
Finned strainer
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.
Finned strainer
The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.
External reactor vessel cooling and electric power generation system
An external reactor vessel cooling and electric power generation system according to the present invention includes an external reactor vessel cooling section formed to enclose at least part of a reactor vessel with small-scale facilities so as to cool heat discharged from the reactor vessel, a power production section including a small turbine and a small generator to generate electric energy using a fluid that receives heat from the external reactor vessel cooling section, a condensation heat exchange section 140 to perform a heat exchange of the fluid discharged after operating the small turbine, and condense the fluid to generate condensed water, and a condensed water storage section to collect therein the condensed water generated in the condensation heat exchange section, wherein the fluid is phase-changed into gas by the heat received from the reactor vessel. The external reactor vessel cooling and electric power generation system according to the present invention can continuously operate even during an accident as well as during a normal operation to cool the reactor vessel and produce emergency power, thereby enhancing system reliability. The external reactor vessel cooling and electric power generation system according to the present invention can easily apply safety class or seismic design using small-scale facilities, and its reliability can be improved owing to applying the safety class or seismic design.