EDN: HVVVVF
Authors & Affiliations
Dmitriev D.V., Jilkin A.S., Markelov V.D., Filimonov E.V.
A.I. Leypunsky Institute of Physics and Power Engineering, Obninsk, Russia
Dmitriev D.V. – Researcher. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 54-21);
e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Jilkin A.S. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Markelov V.D. – Research Intern.
Filimonov E.V. – Senior Researcher, Cand. Sci. (Phys.-Math.).
Abstract
Recently, fast neutron reactors have become one of the most promising areas of development of the nuclear industry in Russia and in the world. They have unique advantages, such as high efficiency of nuclear fuel use and the ability to burn minor actinides, which makes them a key element on the way to a closed fuel cycle.
Correct mathematical modeling of the processes of fission product release from fuel and migration through the working media of the first circuit allows obtaining more reliable estimates when substantiating the radiation safety of existing and designed fast neutron reactors with sodium coolant, as well as in the calculation support of experiments on irradiation of new types of fuel.
The paper presents mathematical models of the yield of fission products from uranium oxide, mixed oxide and mixed nitride fuel, and also provides a brief description of the capabilities of the Alpha-BN 1.0 computer program, designed to obtain calculated estimates of the relative yield of fission products.
Keywords
fast neutron reactor, sodium coolant, computer program, fission product yield, fission products, uranium oxide fuel, mixed oxide fuel, mixed nitride fuel, fuel temperature
Article Text (PDF, in Russian)
References
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UDC 621.039.584
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 3, 3:7
