A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.

Systems repair jet pump elbow joining structures like RS1 and RS2 welds. Systems include a base having legs that secure to ends of the elbow in different directions, and a drive plate that joins to flow conduits where they meet the elbow. The drive plate and base may then be pushed together, resulting in compression or joining of the elbow and flow conduit. Multiple drive plates may be used with a single base to compress multiple flow conduits to the base. The base and the drive plates can be driven together with a driving bolt extending through the base and driving plate. To provide a better fit, grooves can be created in the flow conduits through machining from the installed base. The drive plate may be seated into the groove to achieve a desired orientation with less slippage. Example embodiments and methods do not require welding or a welding base.

Systems repair jet pump elbow joining structures like RS1 and RS2 welds. Systems include a base having legs that secure to ends of the elbow in different directions, and a drive plate that joins to flow conduits where they meet the elbow. The drive plate and base may then be pushed together, resulting in compression or joining of the elbow and flow conduit. Multiple drive plates may be used with a single base to compress multiple flow conduits to the base. The base and the drive plates can be driven together with a driving bolt extending through the base and driving plate. To provide a better fit, grooves can be created in the flow conduits through machining from the installed base. The drive plate may be seated into the groove to achieve a desired orientation with less slippage. Example embodiments and methods do not require welding or a welding base.

A single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected to the throttling device and to a condenser connected to the throttling device, which device is a throttling steam generator vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by horizontal sealed partitions. The high pressure zone is connected to the the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the the horizontal sealed partitions and the high pressure zone. The single-loop nuclear power plant is provided with an electric motor to rotate the impeller.

A single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected to the throttling device and to a condenser connected to the throttling device, which device is a throttling steam generator vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by horizontal sealed partitions. The high pressure zone is connected to the the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the the horizontal sealed partitions and the high pressure zone. The single-loop nuclear power plant is provided with an electric motor to rotate the impeller.

Engineered surfaces, such as surfaces having nano- and/or micro-scale features, may provide an enhanced flow boiling Critical Heat Flux (CHF) at ambient or higher pressures, which may enhance cooling. Enhancing flow boiling CHF may be desirable for nuclear reactors, where heat is generated by a heater such as a nuclear reactor core. Enhanced flow boiling CHF may provide larger safety margins and/or better economics of nuclear reactors, for example, because reactor power rating may be increased as cooling is enhanced.

Engineered surfaces, such as surfaces having nano- and/or micro-scale features, may provide an enhanced flow boiling Critical Heat Flux (CHF) at ambient or higher pressures, which may enhance cooling. Enhancing flow boiling CHF may be desirable for nuclear reactors, where heat is generated by a heater such as a nuclear reactor core. Enhanced flow boiling CHF may provide larger safety margins and/or better economics of nuclear reactors, for example, because reactor power rating may be increased as cooling is enhanced.

A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.

A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.

An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned.