Development of a thermodynamic calculation model for the quasi-stationary simulation of residual heat removal through a closed natural convection cycle in the helium-cooled high-temperature reactor AHTR 500

Automatic translation: Responsible concepts lead to the need for one too medium to long-term use of nuclear energy to secure future Power supply. This realization is reinforced by the increasing Appreciation of the global anthropogenic greenhouse effect. Nevertheless lacking there is a broad social consensus at the moment for the future use of nuclear energy. The crucial focus at the design of advanced nuclear facilities is therefore on the Field of security research, not least to create a factual justifiable public acceptance of nuclear energy as an energy source. Important aspects in postulating advanced safety criteria are the development of coated fuel elements to a large extent direct Restraint of the fission products as well as ensuring an inherent safe residual heat dissipation. The helium-cooled high-temperature reactor meets due to its system properties, namely the large heat capacity of the Fuel elements and the graphite internals as well as the low power density, fundamentally the character of an inherent security philosophy. This here treated reactor AHTR 500 is used to generate nuclear process heat. Compared to the closed single tank design (AVR, THTR 500, HTR 500), in which the entire primary circuit in the reactor pressure vessel is housed and the multi-tank construction (HTR module) in which the Primary circuit components are arranged in directly coupled containers is the AHTR 500 follows a non-integrated design. This means that only the core is enclosed by a pressure vessel and the fans or Process heat exchanger are connected via pipes to the reactor. This outsourcing of the remaining primary circuit components leads to correspondingly smaller dimensions of the reactor pressure vessel.