Description
Chairs: Yougi Zheng and Andrey Fedorovskiy
In the conditions of the modern international market, not only the safety of nuclear facilities, but also their economic performance is critically important. When developing its facilities, the project direction "Proryv" tries to solve these problems comprehensively on the basis of new reactor technologies and closing the nuclear fuel cycle. Given the high degree of novelty of projects, the...
Artificial Neural Networks (ANN) are presented as a very powerful tool for modelling complex systems. This approach is becoming increasingly widespread and it has a great potential for nuclear reactor applications. In this work, an ANN is developed for predicting sodium void effects in a large Sodium Fast Reactor core and their spatial interrelations.
The ultimate goal is to provide more...
Enhancement of efficiency of state-of-the-art computation systems and software modernization make it possible to elaborate computer model development technology to the technology of super-computer twin development. The reactor plant supercomputer twin implies three levels of detailing:
- The upper level model permitting consideration of effects of non-isothermal coolant flows, distribution...
Concept of the BREST reactor with lead coolant and dense heat-conductive nitride fuel envisages the development of an equilibrium core with complete breeding of fissionable nuclides in the core (core breeding ratio of ~ 1) without a blanket compensating for reactivity reduction due to fuel burn-up and fission product build-up. This makes it possible to operate the reactor in the period between...
Westinghouse continues to develop its Next Generation high-capacity nuclear power plant (NPP) based on Lead‐cooled Fast Reactor (LFR) technology. By leveraging its long experience in NPP commercialization as well as strategic domestic and international partnerships established to most effectively complement capabilities, Westinghouse is progressing the plant’s design and its business and...
Two types of mixed uranium-plutonium fuel are considered for BN-1200 reactor within the framework of “Proryv” project: conventional, well-mastered MOX-fuel and advanced mixed uranium-plutonium nitride (MNUP) fuel having higher density.
The main design mode of reactor operation is operation in the equilibrium mode with scattered batch refuelings. As compared with equilibrium state, the...
To solve problems of BN-800 transition from the hybrid core consisting of FSAs with pellet-type uranium oxide fuel and FSAs with pellet-type and vibropacked MOX-fuel to the core loaded completely with pellet-type MOX-fuel, it is necessary to develop and implement a proper core design.
In the developed design it is provided that the transition is performed by replacement of hybrid core spent...
