A generator is installed on and provides electrical power from a turbine by converting the turbine's mechanical energy to electricity. The generated electrical power is used to power controls of the turbine so that the turbine can remain in use through its own energy. The turbine can be a safety-related turbine in a nuclear power plant, such that, through the generator, loss of plant power will not result in loss of use of the turbine and safety-related functions powered by the same. Appropriate circuitry and electrical connections condition the generator to work in tandem with any other power sources present, while providing electrical power with properties required to safely power the controls.

A generator is installed on and provides electrical power from a turbine by converting the turbine's mechanical energy to electricity. The generated electrical power is used to power controls of the turbine so that the turbine can remain in use through its own energy. The turbine can be a safety-related turbine in a nuclear power plant, such that, through the generator, loss of plant power will not result in loss of use of the turbine and safety-related functions powered by the same. Appropriate circuitry and electrical connections condition the generator to work in tandem with any other power sources present, while providing electrical power with properties required to safely power the controls.

A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

A method of governing a pressurized water nuclear reactor can simultaneously consider and balance a large number of control goals. The method includes iteratively considering a large number of randomly varied possible trajectories (Ta) of actuating variables for controlling reactor core reactivity for a future time interval. Each trajectory (Ta) of actuating variables is assigned a figure of merit (Σ) on the basis of a Value Table which contains weighting or penalty values for a number of events or adverse reactor core states which are characterized by preset conditions or values of the actuating variables, the process variables and/or variables derived from them. The trajectory (Ta) of actuating variables is chosen such that the figure of merit (Σ) has a local extremum, and corresponding actuators are moved accordingly.

A method of governing a pressurized water nuclear reactor can simultaneously consider and balance a large number of control goals. The method includes iteratively considering a large number of randomly varied possible trajectories (Ta) of actuating variables for controlling reactor core reactivity for a future time interval. Each trajectory (Ta) of actuating variables is assigned a figure of merit (Σ) on the basis of a Value Table which contains weighting or penalty values for a number of events or adverse reactor core states which are characterized by preset conditions or values of the actuating variables, the process variables and/or variables derived from them. The trajectory (Ta) of actuating variables is chosen such that the figure of merit (Σ) has a local extremum, and corresponding actuators are moved accordingly.

To reduce a corrosion damage risk to a heat transfer tube of a steam generator while suppressing the use of chemicals having environmental effects. A pressurized water nuclear power plant includes a hydrogen supply unit configured to supply hydrogen to a water single phase part of a secondary system, a hydrogen concentration measuring unit configured to measure hydrogen concentration in the water single phase part, and a control unit configured to control supply of hydrogen by the hydrogen supply unit so that the hydrogen concentration measured by the hydrogen concentration measuring unit exceeds 10 ppb.

To reduce a corrosion damage risk to a heat transfer tube of a steam generator while suppressing the use of chemicals having environmental effects. A pressurized water nuclear power plant includes a hydrogen supply unit configured to supply hydrogen to a water single phase part of a secondary system, a hydrogen concentration measuring unit configured to measure hydrogen concentration in the water single phase part, and a control unit configured to control supply of hydrogen by the hydrogen supply unit so that the hydrogen concentration measured by the hydrogen concentration measuring unit exceeds 10 ppb.

A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

This patent application is for a process of nuclear power generation with ˜KW output by making the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 in a Thorium Molten Salt Reactor (Th-MSR) to undergo fission along the thorium fuel cycle by providing thermal neutrons which were obtained by slowing down of fast neutrons from n external neutron generators with the help of graphite moderators carefully arranged inside the Th-MSR.

The molten salt that entered the reactor at a temperature of 600° C. becomes hot to 750° C. due to nuclear fission, goes through a heat exchanger and returns to the reactor. The output power of this reactor is proportional to the number of thermal neutrons supplied to the inside of the reactor, and when the external neutron generator is turned ON-OFF, nuclear power generation is also ON-OFF.

This Th-MSR power generation process with thermal neutron generators, which Dr. Choi is applying for a patent, will be one of the most innovative ways to generate ˜kW range nuclear power with the use of 100% non-radioactive nuclear fuel since until now all the Th-MSR power generation scheme relied upon neutrons from the natural decay of Uranium-235 mixed with the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 with a mixing ratio of 80% ThF4 to 20% UF4. Key Word Thorium Molten Salt Reactor, Thermal Neutron Generator

This patent application is for a process of nuclear power generation with ˜KW output by making the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 in a Thorium Molten Salt Reactor (Th-MSR) to undergo fission along the thorium fuel cycle by providing thermal neutrons which were obtained by slowing down of fast neutrons from n external neutron generators with the help of graphite moderators carefully arranged inside the Th-MSR.

The molten salt that entered the reactor at a temperature of 600° C. becomes hot to 750° C. due to nuclear fission, goes through a heat exchanger and returns to the reactor. The output power of this reactor is proportional to the number of thermal neutrons supplied to the inside of the reactor, and when the external neutron generator is turned ON-OFF, nuclear power generation is also ON-OFF.

This Th-MSR power generation process with thermal neutron generators, which Dr. Choi is applying for a patent, will be one of the most innovative ways to generate ˜kW range nuclear power with the use of 100% non-radioactive nuclear fuel since until now all the Th-MSR power generation scheme relied upon neutrons from the natural decay of Uranium-235 mixed with the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 with a mixing ratio of 80% ThF4 to 20% UF4. Key Word Thorium Molten Salt Reactor, Thermal Neutron Generator