NuScale Power, LLC

A nuclear power plant system, comprising a crane, a nuclear reactor, and a plurality of instruments, wherein an instrument of the plurality is configured to monitor a parameter of the nuclear power plant system, each instrument of the plurality is configured to transmit data to a local data collection system, and each instrument of the plurality is configured to transmit the data to an external data collection system.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

A nuclear power plant comprising at least one nuclear reactor having a steam generator, a steam cycle including the steam generator, a first turbine fluidly coupled to the steam generator, a first condenser fluidly coupled to the first turbine, and a feedwater heater fluidly coupled to the first condenser and the steam generator, an intermediate thermal loop including the first condenser, and an evaporator, and an organic cycle including the evaporator, a second turbine fluidly coupled to the evaporator, a second condenser fluidly coupled to the second turbine, and a heat exchanger fluidly coupled to the second condenser and the evaporator.

An integrated energy system comprising a power plant configured to generate steam. The power plant can include a nuclear reactor and/or an electrical power generation system. A chemical products generation system can include a first reaction chamber receiving Sodium Formate (HCOONa) that, via insertion of a first portion of the steam at a first temperature, is decomposed into Sodium Oxalate ((COO) 2 Na 2 ) and Hydrogen (H 2 ), the steam including super-heated steam. The chemical products generation system can include a second reaction chamber receiving the Sodium Oxalate ((COO) 2 Na 2 ) that, via insertion of a second portion of the steam at a second temperature, is decomposed into Sodium Oxide (Na 2 O), Carbon Monoxide (CO), and Carbon Dioxide (CO 2 ). A syngas generation system can be operably coupled to the chemical products generation system and configured to generate a combination of the Hydrogen (H 2 ), the Carbon Monoxide (CO), and/or the Carbon Dioxide (CO 2 ), and/or to generate syngas.

Methods and systems for hydrogen production from inert sodium salts are described herein. In an example method, steam is generated by a nuclear reactor power plant system. The steam is applied to sodium formate to facilitate one or more thermal and/or hydrothermal decomposition processes, thereby generating hydrogen. In the example method, sodium formate is generated by combining sodium hydroxide generated by an electrolysis process with sodium carbonate and/or sodium bicarbonate generated by a carbon capture process. Embodiments can be used to supply hydrogen storage facilities and/or for energy production.

A flow control system comprising a steam generator (SG) having an inlet and an outlet, the SG including a plurality of SG tubes extending from the inlet to the outlet, a primary coolant system configured to transfer heat to the SG, a steam valve fluidly connected to the outlet of the SG, and an SG level control system configured to operate the steam valve based at least in part on an approach temperature.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

A steam generation system, comprising a first heat exchanger to discharge steam having a first pressure, a gas compressor discharge steam at a second pressure, the gas compressor including a first impeller made of a first material, a second impeller made of a second material, and a shaft, an auxiliary heater to receive steam at a first temperature and discharge the steam at a second temperature, an industrial processing plant to receive the steam at the second temperature and discharge a fluid, a pump to receive and discharge a the fluid, and a second heat exchanger to receive the fluid at a temperature and discharge the fluid at a higher temperature to the first heat exchanger.

Techniques for latching a shaft assembly with an integrated system are discussed herein. The integrated system including a nuclear reactor configured to raise a stem of the shaft assembly into a hold out. The hold out can include a sleeve, and metallic balls, the metallic balls being positioned in openings of the sleeve. The hold out can include a housing positioned around the sleeve and the metallic balls. The housing can include a gap that is narrower than a chamber of the housing. The hold out can include a spring coupled to the sleeve. The hold out can include an electromagnetic coil configured to engage the spring and the sleeve to raise the stem until the metallic balls are moved from positions between the gap of the housing and the stem, to positions between the chamber of the housing and the stem.

Pressure vessels and closures for pressure vessels, such as for use in nuclear reactor systems, are described herein. A representative pressure vessel includes (i) a first enclosure including a first flange having a lower surface and a first inner surface, and (ii) a second enclosure including a second flange having an upper surface and a second inner surface. The pressure vessel can further include a sealing member having a first portion and a second portion. The first portion is configured to contact both the lower surface of the first flange and the upper surface of the second flange to provide a first seal between the first and second enclosures. The second portion is configured to contact, via an interference fit, both the first inner surface of the first flange and the second inner surface of the second flange to provide a second seal between the first and second enclosures.