EDN: FCCIQG
Authors & Affiliations
Isanov K. A., Susakin V. A., Zakirov N. A., Eliseev V. 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, 249033. Tel: +7 (981) 711-92-65; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Susakin V.A. – Trainee.
Zakirov N.A. – Research Engineer.
Eliseev V.A. – Leading Researcher.
Gulevich A.V. – Head of Reactor Physics Department, Dr. Sci. (Phys.-Math.).
Abstract
In this paper a comparative analysis of the efficiency of homogeneous burning in MOX- and SNUP-fuel of BN-1200 type reactor is carried out in the realization of material flow of americium of 100 and 200 kg/year through the core. Plutonium of different isotopic composition is considered. Accumulation and burnup of americium in MOX- and SNUP-fuel with plutonium of different isotopic composition and different amount of americium in fresh fuel have been evaluated. A comparative analysis of accumulation rates and efficiency of americium burnup in MOX- and SNUP-fuel has been performed. The rates and volumes of curium accumulation during americium burning in MOX- and SNUP-fuel with plutonium of different isotopic composition are estimated. Specific estimation of curium accumulation per mass unit of burned americium – curium burden is given. A comparative analysis of the rates and volumes of curium accumulation during the burning of americium in MOX- and SNUP-fuel, as well as a comparison of the specific curium accumulation per mass unit of burned americium is performed. The total mass balance of minor actinides in the system, taking into account the rates and volumes of burned americium and accumulated curium, is also estimated. The number of reactor-years required to burn 1 ton of americium using BN SNF plutonium in MOX- and SNUP-fuel was determined. The number of recycles to achieve 90 % burnup of the initial amount of americium in MOX- and SNUP-fuel has also been determined.
Keywords
americium burnout, transmutation, curium accumulation, plutonium isotopic composition, BN-1200 reactor, MOX-fuel, SNUP-fuel
Article Text (PDF, in Russian)
References
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UDC 621.039.54(04)
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:7
