Physics behind the Concept of a Sodium-Potassium-Cesium-Cooled Martian Nuclear Reactor

Abstract

The main goal of the work is to determine the basic conceptual solutions of a nuclear reactor operating on the surface of another planet. The problem was solved using the example of the Martian nuclear power plant. The article uses calculation and optimization research methods and corresponding program codes (well-known and author's). The results of the study made it possible to formulate the basic requirements for the Martian nuclear power plant and select the type of reactor. This is a new type of reactor: pressurized liquid metal fast reactor. It is proposed to use an innovative cermets nuclear fuel based on mixed mononitride and uranium metal nanopowder, which was previously considered by the author for new generation BN and BREST ground-based reactors. It is proposed to use a eutectic (or near-eutectic) NaKCs alloy as a coolant. Optimization of the alloy composition has been carried out. The fuel and coolant of the reactor contains long-lived radioactive waste to be transmuted. NaKCs alloy is less reactive than pure alkali metals including Na, K and Cs. With an electric power of 600 MW, it is possible to ensure the internal self-protection of the reactor. All emergency modes of the ATWS type (anticipated transient without scram) are not hazardous. This means that with a decrease in power to values characteristic of the initial stages of the colonization of Mars, the safety of the reactor is easily ensured. The relatively low chemical activity of the coolant makes it possible to use a two-circuit energy conversion scheme. The second circuit can use water or carbon dioxide. Carbon dioxide is preferred because of its presence in the atmosphere of Mars (95% CO2). The significance of the research lies in the possibility of constructing a Martian nuclear power plant within the framework of existing technologies.