Abstract

In this work, we study the features of the spatial kinetics of installation as a hybrid thorium reactor with an elongated plasma neutron source based on a magnetic trap. The active zone of the installation under study consists of an assembly of hexagonal fuel blocks of a unified design and a long solenoid with a high-temperature plasma column passing through the axial region of the core. Combining engineering expertise in creating nuclear reactors with a physics-technical potential for obtaining high-temperature plasma in a long magnetic trap we ensure the solution of the multidisciplinary problem posed. These studies are of undoubted practical interest, since they are necessary to substantiate the safety of operation of such hybrid systems. The research results will allow optimizing the active zone of the hybrid system with leveling the resulting offset radial and axial energy release distributions. Results of our study will be the basis for the development of new and improvement of existing methods of criticality control in related systems such as “pulsed neutron source – subcritical fuel assembly”

Highlights

  • A special feature of the reactor studied in the work [1, 3] is that it is able to produce heat, electricity energy and hydrogen simultaneously, and its core can rather be modified for solving another task [4]

  • A special facility intended for studying neutronic properties of the dispersion (Th,Pu)O2 fuel was suggested in the capacity of such installation by the employee group of Budker Institute of Nuclear Physics of SB RAS (Novosibirsk, Russia) [4,5,6]

  • This facility is an assembly of fuel blocks the axial part of which is substituted by a long magnetic trap [5,6] with high temperature plasma providing generation of thermonuclear neutrons

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Summary

Introduction

A special feature of the reactor studied in the work [1, 3] is that it is able to produce heat, electricity energy and hydrogen simultaneously, and its core can rather be modified for solving another task [4]. This facility is an assembly of fuel blocks the axial part of which is substituted by a long magnetic trap [5,6] with high temperature plasma providing generation of thermonuclear neutrons.

Results
Conclusion

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