Hydrogen as an energy carrier will play a considerable role in the future structure of energy production when nuclear reactors will replace fossil fuels. Investigations performed in recent years have shown that the production of large quantities of energy with high efficiency can be accomplished on the basis of thermochemical cycles using reactors with coolant temperature at the exit from the core of about 900°C. A variant of such a fast reactor with sodium as the coolant is proposed. The main physical characteristics and the main problems which must be solved to build such a reactor are presented. According to its properties, this reactor will meet the modern requirements for nuclear and radiation safety. It can also be used in other promising high-temperature technologies, for example, high-efficiency production of electricity.According to modern ideas, reactors with coolant temperature ~900°C at the exit from the core will play a large role in the future structure of nuclear structure. They will make it possible to solve important problems such as the production of hydrogen in large quantities, making electricity production more efficient, and expanding the use of high-temperature technology in industry.High-temperature helium-cooled reactors are now being considered for this purpose. For example, designs of a modular thermal helium reactor GT-MHR [1] with gas-turbine energy conversion and a fast GFR [2] for use in hydrogen production using an iodine-sulfur water separation cycle without the formation of greenhouse gases are being developed in the USA and some other foreign countries. In our country, a group of enterprises at the forefront with the Russian Science Center Kurchatov Institute [3] has developed a technical proposal for developing an electrotechnical facility on the basis of a thermal high-temperature helium HTGR for a chemical-industrial process for steam conversion of methane or products of gasification of coal with a low calorific value.
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