Description
Chairs: Alina Constantin
When transferring to two-component nuclear energy system at the initial stage of closing the nuclear fuel cycle of Russia, the number of fast breeder reactors BN type fuelled with plutonium do exist to a small extent and stocks of separated plutonium already are sizable and continue to grow due to pilot reprocessing SNF of VVER. Therefore, for this period of time, it is proposed to abandon...
The European project PUMMA (Plutonium Management for More Agility) is dedicated to the different Pu management options in 4th generation systems to assess the impact on the entire fuel cycle. Fast neutron reactors with associated fuel cycle strategies have been chosen to cope with these options because they are flexible: they offer the possibility of isogeneration, burning or breeding of...
The Russian Federation is developing a number of technologies within the «Proryv» project for closing the nuclear fuel cycle utilizing mixed (U-Pu-MA) nitride fuel. Key objectives of the project include improving fast reactor nuclear safety by minimizing reactivity changes during fuel operating period and improving radiological and environmental fuel cycle safety through Pu multi-recycling and...
China already has 48 nuclear power reactors in operation, and 12 nuclear power reactors under construction till June，2020. The accumulated spent fuel in China has exceeded 8,500 tons. China implements the established policy of closed nuclear fuel cycle for the sustainable development of nuclear power. However, there seems no feasible development plan and road map to initiate and deploy a...
The current stage of nuclear power development is often characterized by directly opposite trends: on the one hand, there is a growing understanding of the need to transition to a closed fuel cycle, and on the other hand, there is a very large uncertainty about the growth rates of nuclear power capacity. In such conditions, the main driver of the transition to SNF is not the need for capacity...
Within the Generation IV International Forum, the partners of the Sodium-cooled Fast Reactor System Arrangement (China, Euratom, France, Japan, Korea, the Russian Federation, The United Kingdom and the United States of America) completed an evaluation of SFR advanced fuel options. This work was based on a preliminary work performed in the GIF SFR Advanced Fuel Project. It entailed a comparison...
In Russia, it is planned to build a pilot demonstration fast lead-cooled reactor with an electric power of 300 MW (BREST-OD-300). Mixed nitride U-Pu fuel with minor actinides (MA) of energy composition will be used as nuclear fuel. Plutonium will be taken from the spent nuclear fuel (SNF) of a VVER-440. The isotopic composition of power plutonium can be different due to different storage...
The purpose of this work was to study and identify the features of the formation of external radiation doses to personnel during the production of a new mixed uranium-plutonium nitride fuel, which surpasses MOX fuel in almost all thermal and physical characteristics, the production of which is currently being developed in Russia.
Quite a few works have been devoted to the radiation...
