BANTER represents the first step towards realizing an innovative bimodal nuclear thermal and electric propulsion system in which the same fluid (i.e. ammonia) is used as a propellant for thermo-nuclear propulsion and electric thrusters and as a working fluid for the power generation system. Due to its ease of storage in non-cryogenic conditions, its presence as an in-situ resource on many targets of future space missions, and its possibility of decomposing to increase the propulsive performance, ammonia allows the development of a compact propulsion system capable of transporting tons of payloads for a wide spectrum of missions. The design and verification through analysis of a nuclear reactor implementing a new type of coolant channels and a radiator-less power generation system fed by ammonia will constitute the first phase of this process. Then, the combination of the thermolysis, catalysis, and radiolysis processes to decompose the ammonia will be studied through two experimental campaigns carried out on prototypes of the coolant channels both in a nuclear and non-nuclear environment with the aim of demonstrating propulsive performance capable of outclassing traditional chemical propulsion systems. Moreover, another phase of design, development, and testing will demonstrate the ability of a cluster of newly designed ammonia electric thrusters to operate for long periods without excessive cathode erosion, eventually with increased efficiency due to the catalytic decomposition of the propellant. Positive outcomes of the project will pave the way for developing a technology that could make Europe a protagonist of the future space race thanks to a compact, versatile, and high-performance propulsion system. In addition, any improvement in the production of green hydrogen from ammonia decomposition will benefit also for the energy industry. This aspect makes this project highly multidisciplinary not only in the research approach but also in the results.

Raising nuclear reactor safety to a higher level - The supercritical CO2 heat removal system - "sCO2-HeRo" The “supercritical CO2 heat removal system”, sCO2-HeRo, safely, reliably and efficiently removes residual heat from nuclear fuel without the requirement of external power sources. This system therefore can be considered as an excellent backup cooling system for the reactor core or the spent fuel storage in the case of a station blackout and loss of ultimate heat sink. sCO2-HeRo is a very innovative reactor safety concept as it improves the safety of both currently operating and future BWRs and PWRs through a self-propellant, self-sustaining and self-launching, highly compact cooling system powered by an integrated Brayton-cycle using supercritical carbon dioxide. Since this system is powered by the decay heat itself, it provides new ways to deal with accidents that are beyond design. The sCO2-HeRo provides breakthrough options with scientific and practical maturity, which will be proven by means of numerical tools, like advanced CFD, and small-scale experiments to determine the performance of the components like a compact heat exchanger and a turbo-machine set. A demonstration unit of the sCO2-HeRo system will be installed in a unique glass model in order to demonstrate the maturity of the system. Finally, the potential of this system to deal with a range of different accident scenarios and beyond-design accidents will be shown with the help of the German nuclear code ATHLET.

After a common expression of willingness to cooperate and legal establishment of V4G4 Centre of Excellence Association, VINCO project represents the next stage of capacity building in nuclear technologies in Central European countries. Participating countries defined already their specializations: helium technology in Czech Republic, design and safety analyses in Slovakia, fuel studies in Hungary and material research in Poland. Having such expertise, the joint development of Gen IV nuclear technologies with the special emphasis on gas-cooled reactors is fully possible. Thus, the main objectives of the regional VINCO project are: (i) development of the principles of cooperation and rules of access to existing and planned infrastructure, (ii) identification of the specific objectives of the R & D activities in the cooperating countries, (iii) description and analysis of the existing research, training and educational equipment and capabilities, (iv) determination of the investment priorities in cooperating countries and (v) setting up of joint research, educational and training projects. It is expected that the joint activities will result in coordination of actions allowing to obtain financing from the Structural Funds available for the Visegrad countries. These funds would allow for a huge increase of mass and modernization of the research potential in the region. Close cooperation with other EU institutions (mainly CEA, France) will ensure better description of the investments needed in Visegrad Region, tightening of pan-European cooperation and strengthening of the role of V4 countries, helping them to evolve from users to the suppliers of R&D capabilities in nuclear technologies. A major expected impact of the project would be setting up of a distributed regional research centre specialized in nuclear technologies needed to develop Gen IV reactors and to improve safe operation of existing and planned Nuclear Power Plants in the region.