DOI: 10.55176/2414-1038-2019-2-243-255
Authors & Affiliations
Belov A.A.1, Bereznev V.P.1, Seleznev E.F.1, Shkarovsky D.A.2, Zherdev G.M.3
1 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
2 NRC “Kurchatovskiy Institute”, Moscow, Russia
3 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Belov A.A. – Scientific collaborator, Nuclear Safety Institute of Russian Academy of Sciences. Contacts: 52, Bolshaya Tulskaya st., Moscow, Russia, 115191. Tel: +7(495)955-23-11; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Bereznev V.P. – Scientific collaborator, Cand. Sci. (Tech.), Nuclear Safety Institute of Russian Academy of Sciences.
Seleznev E.F. – Head of laboratory, Dr. Sci. (Tech.), Nuclear Safety Institute of Russian Academy of Sciences.
Shkarovsky D.A. – Head of the Division of Benchmark Calculations of Nuclear Reactors, Cand. Sci. (Phys. and Math.), NRC “Kurchatovskiy Institute”.
Zherdev G.M. – Leading researcher, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Abstract
The paper presents a software package for justifying radiation safety is developed as part of the neutron-physical calculation modules for fuel-containing components based on diffusion approximation, Sn approximation and Monte-Carlo method, nuclide kinetics calculation module, radiation sources calculation module, direct radiation field calculation modules (PS) based on the Sn approximation and the Monte Carlo method together with the constant support system.
Since it was planned to use ready-made independent calculation modules, the main problem was to organize the joint work of the calculation modules within the radiation safety justification code by developing a methodology for combining the modules into a calculation chain and creating the necessary tools for this.
At present, the code being developed is ready for one-time calculations by developers. The field of application is the cores of fast reactors, fuel and irradiated non-fuel materials storage units, objects of a closed nuclear fuel cycle.
Keywords
radiation safety, nuclide kinetics, transport approximation, Monte Carlo method, radioactive source, irradiated nuclear fuel
Article Text (PDF, in Russian)
References
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UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:24
