PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

INVESTIGATION OF AMERICIUM MULTIPLE RECYCLING DURING HOMOGENEOUS BURNING IN A BN-TYPE REACTOR

EDN: CTAMXB

Authors & Affiliations

Isanov K.A., Zakirov N.A., Gulevich A.V.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Isanov K.A. – Research Engineer. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (981) 711-92-65; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zakirov N.A. – Research Engineer.
Gulevich A.V. – Head of Reactor Physics Department, Dr. Sci. (Phys.-Math.).

Abstract

The development of nuclear power engineering and transition to the ZNFC requires solving the problem of accumulation and management of long-lived radioactive waste (minor actinides), to reduce the potential hazard in the long term, as well as reducing the volume of borosilicate matrix for vitrification and RW disposal. One of the most effective methods of MA utilization is homogeneous burning in a BN-type reactor. The efficiency and rates of homogeneous burning range from 19 to 45 % and from 35 to 85 kg/year, respectively, depending on the isotopic composition of the plutonium used. Thus, multiple recycling of americium is necessary to achieve a homogeneous burnup efficiency of 90 %.
In this paper, a computational model of the BN-1200 type reactor is compiled and the core is modeled for the steady-state overload mode. The fraction of makeup plutonium was determined. Seven types of plutonium have been considered to study the efficiency of homogeneous burning at multiple recycling. The comparative analysis of the burnout efficiency is performed at realization of equality of passing americium mater flows through the core with MOX fuel of different isotopic composition, amounting to 189 kg/year.
The rates and efficiency of americium burnup, curium accumulation rates, and the total balance of minor actinides in the system under multiple recycling of americium in MOX fuel with plutonium of different isotopic composition have been determined. The influence of multiple recycling of americium on the design heat release limitations for STVS and SFAs has been investigated, and limiting factors have been determined. The paper also determines the influence of the structure of the closed nuclear fuel cycle and the strategy for organizing the passage of plutonium material flows in the ZNFC through a BN-type reactor on the efficiency, rates, and feasibility of homogeneous recycling of minor actinides under various conditions.

Keywords
americium burnup, multiple recycling of americium, transmutation, curium, plutonium isotopic composition, BN-1200 type reactor, MOX fuel

Article Text (PDF, in Russian)

References

UDC 621.039.54(04)

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 3, 3:4