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Development and characterization of a prototype selenium-75 high dose rate brachytherapy source. [PDF]
Med PhysKalinowski J +6 more
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NEUTRON-PHYSICAL CALCULATION OF THE VVER-1000 ON MOX-FUELED REACTOR
Energy Systems, 2023The use of mixed uranium-plutonium fuel in thermal reactors makes it possible to effectively use highly toxic weapons-grade plutonium for peaceful purposes. The world's reserves of such plutoni-um are a serious problem. The use of this fuel in thermal reactors significantly reduces the amount of enriched uranium needed, as well as to dispose of ...
Mikle Egorov, Alexander Blinnikov
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Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark
Progress in Nuclear Energy, 2015Abstract In this work, OpenMC code has been used for reactor physics calculations of the IAEA 10 MW MTR benchmark. To perform the burnup dependent studies i.e. Beginning of Life (BOL) and End of Life (EOL) calculations are carried out using OpenMC.
Khurrum Saleem Chaudri +1 more
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Neutron-Physical Calculations of a Nuclear Reactor: Computing Time Reduction by Digital Filtration
Atomic Energy, 2015An algorithm is proposed for performing neutron-physical calculations of a reactor using digital signal processing methods. It is shown that the algorithm’s combined use of the classical methods of numerical analysis and high-frequency digital filters makes it possible to calculate accurately and rapidly the neutron macrofield on a coarse grid and to ...
A. M. Zagrebaev, V. N. Samanchuk
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Some methods of neutron-physical calculation in the profiling of power reactors
The Soviet Journal of Atomic Energy, 1962The article states the problem of neutron-physical calculation for a reactor with uniformization of operating conditions of heat-generating elements by redistribution of the fissionable material. Methods are given for the solution of the problem for different types of reactors (thermal reactors, intermediate reactors with various reflectors and without
N. N. Ponomarev-Stepnoi, E. S. Glushkov
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Neutron-Physical Calculation of a Fresh Zone in the Natural Nuclear Reactor at Oklo
Atomic Energy, 2005A full-scale computer model of zone 2 of the Oklo reactor with a realistic materials composition is constructed. Modern Monte Carlo programs are used to calculate the multiplication factor, the excess reactivity, and the neutron flux for the fresh reactor zone 2.
Yu. V. Petrov +4 more
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Journal of Nuclear Engineering and Radiation Science, 2021
Abstract The main purpose of this work is to study the possibility of using the few-group approximation for calculation of some neutron-physical characteristics of VVER-1000 core by means of special version of Monte Carlo Universal code. The Monte Carlo method for VVER-1000 core neutron-physical characteristics calculation using the few ...
A. S. Bikeev +4 more
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Abstract The main purpose of this work is to study the possibility of using the few-group approximation for calculation of some neutron-physical characteristics of VVER-1000 core by means of special version of Monte Carlo Universal code. The Monte Carlo method for VVER-1000 core neutron-physical characteristics calculation using the few ...
A. S. Bikeev +4 more
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Physics of Particles and Nuclei Letters, 2020
A neutron-physical calculation is performed for neutron-producing lead, tungsten, and natural uranium targets for a subcritical assembly controlled by a proton accelerator at 0.6, 1, and 2.5 GeV. At these high proton energies, the interaction of protons with target atoms is accompanied by a splitting reaction.
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A neutron-physical calculation is performed for neutron-producing lead, tungsten, and natural uranium targets for a subcritical assembly controlled by a proton accelerator at 0.6, 1, and 2.5 GeV. At these high proton energies, the interaction of protons with target atoms is accompanied by a splitting reaction.
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Particulars of neutron-physical calculations of sodium-cooled fast reactors with mixed oxide fuel
Atomic Energy, 2011The neutron-physical characteristics of reactor systems with a fast spectrum, sodium coolant, and uraniumplutonium fuel load have been analyzed on the basis of computational studies of the BFS-62-3A critical assembly and a BN-600 hybrid core with mixed oxide fuel.
E. F. Mitenkova, N. V. Novikov
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