2023, Issue 1

EDN: CRPXCC

Authors & Affiliations

Balovnev A.V., Davidov V.K., Zhirnov A.P., Moiseev A.V., Soldatov E.O.
N.A. Dollezhal Research & Development Institute of Power Engineering, Moscow, Russia

Balovnev A.V. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Davidov V.K. – Senior Researcher.
Zhirnov A.P. – Deputy Head of Department.
Moiseev А.V. – PhD (Phys.-Math.), Scientific Supervisor of the BREST-OD-300 project, Cand. Sci. (Phys.-Math.).
Soldatov E.О. – Lead Engineer, Contacts: 2/8 Malaya Krasnoselskaya st., Moscow, Russia, 107140. Tel.:  +7 (499) 763-04-57; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

Currently, an actual and important task in the development of nuclear energy is the transmutation of produced minor actinides, in particular, americium. In this regard, investigation was made of the neutron-physical characteristics during the transmutation of americium at the designed BR-1200 reactor, which meets the modern requirements of new generation reactors. The study considers homogeneous and two heterogeneous options for americium transmutation in the reactor core. In a homogeneous option, americium in the form of AmN nitride is uniformly mixed in the fuel composition of each fuel element of each fuel assembly of the core. In the first heterogeneous variant, americium is located in the area of the side reflector blocks. In the scenario under consideration, americium dioxide AmO₂ particles are distributed in two types of matrices: an inert magnesium oxide matrix and a depleted uranium matrix. In the second heterogeneous variant, americium nitride pellets are located in the upper gas collector above the fuel column of the fuel elements. In the study under consideration, the starting load americium (isotope ²⁴¹Am) differs from the isotopic composition of regenerated americium (²⁴¹Am, ^242mAm, ²⁴³Am). In modeling, neptunium 237 is returned to the closed fuel cycle, curium isotopes are not returned. Americium burning study in the BR-1200 was carried out taking into account the accumulation of daughter minor actinides. Modeling of minor actinides was performed using the code system developed at JSC NIKIET.

Keywords
transmutation, americium, lead coolant, fast reactor, BR-1200, neutron-physical characteristics, minor actinides, CNFC, homogeneous option, heterogeneous option

Article Text (PDF, in Russian)

References

UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 1, 1:8