Results 251 to 260 of about 130,744 (269)

Application of multiprocessor computers in neutron-physical calculations of reactors

Atomic Energy, 1994
The use of several combinations of computer hardware and software for performing neutron-physical calculations of reactors is broadly outlined. The computer applications are discussed within the criteria of availability and applicability to Russian RBMK-type reactors. The paper focuses primarily on processing speed. Several types of parallel processors
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Neutron-physical and thermohydraulic calculations of VVR-SM with high-and low-enrichment uranium fuel assemblies

Atomic Energy, 2008
The VVR-SM reactor at the Institute of Nuclear Physics of the Academy of Sciences of Uzbekistan is being converted from fuel assemblies with high-enrichment uranium (36% 235U) to fuel assemblies with low-enrichment uranium (19.7% 235U). During the conversion process consisting of nine cycles, the IRT-3M fuel assemblies with high-enrichment uranium ...
S. A. Baitelesov, A. A. Dosimbaev, F. R. Kungurov, U. S. Salikhbaev   +3 more
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GEFEST800 Software System for On-Line Calculations of BN-800 Neutron-Physical Characteristics in a Nonstationary Regime

Atomic Energy, 2015
The GEFEST800 software system developed for performing on-line calculations of the BN-800 reactor contains moduli for performing nonstationary neutron-physical calculations of a reactor, calculations of feedbacks via calculations of the temperature, burnup, residual heat release, evaluations of the activity of spent fuel assemblies, and so forth.
D. S. Asatryan, A. A. Belov, V. I. Belousov, V. P. Bereznev, D. V. Ivchenko, E. F. Seleznev, I. S. Chernova, K. V. Kartashov, A. A. Peregudov, K. F. Raskach, M. Yu. Semenov, A. P. Sorokin, A. M. Tsibulya, A. A. Yakunin, Yu. Yu. Drobyshev, S. A. Karpov, I. V. Fedorov   +16 more
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Statistical verification of neutron-physics programs for calculations in support of nuclear safety

Physics of Atomic Nuclei, 2012
An algorithm for statistical verification of the XT26 code contained in the SAPHIRE-2006 code system is described. The results of conservative estimation of the calculation error in the Keff calculations for different types of benchmark experiments are presented.
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Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

Progress in Nuclear Energy, 2016
Abstract As part of recent efforts to utilize NPPs computational methodologies to safety analysis of research reactors, the Serpent and DYN3D codes were extensively compared with a variety of static and burnup calculations as defined in the IAEA benchmark for 10 MW MTR pool-type reactor. These calculations include unit cell calculations and few group
Marat Margulis, Erez Gilad
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Evaluation of the systematic error of Monte Carlo calculations of neutron-physical properties using a multiprocessor computer

Atomic Energy, 2011
Algorithms for evaluating the systematic error of Monte Carlo calculations performed using different variants of an approximate solution of a homogeneous neutron transport equation (the method of a constant number of points of division and augmentation, and others), when the number of neutrons per generation is reduced to a number set a priori, are ...
M. A. Kalugin, D. S. Oleinik, E. A. Sukhino-Khomenko   +2 more
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Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor

Atomic Energy, 2017
A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used. The computational results are used as a basis for comparing the self-protection of a reactor with a sodium cavity ...
Yu. M. Ashurko, A. V. Volkov, K. F. Raskach, N. V. Solomonova   +3 more
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Precision Calculations of Some Neutron-Physical Characteristics of VVER-1000 Using the MCU Code

Atomic Energy, 2015
Highly detailed computational models of the reactors in the Nos. 2 and 3 units at the Rostov NPP and the No. 3 unit at the Tianwan NPP (China) with the first fuel load are briefly described. Calculations of two states of the reactors were performed with the MCU code, implementing the Monte Carlo method, for each model: at the lowest controllable power ...
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The Measurement of Fast Reactor Irradiated Minor Actinides and Comparison with Neutron Physics Calculations

1992
Pellets of ten different mixtures of actinide oxides including thorium, neptunium, uranium, plutonium of different isotopic compositions and americium were irradiated in the Material Testing Element 2 (MTE 2) in the reflector of the KNKII/2 reactor, Karlsruhe from August 1983 to October 1985.
L. Koch, K. Kammerichs, R. Wellum, I. Broeders, B. Krieg, T. Matsumura   +5 more
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GEFEST800 Software Complex for Performing Real-Time Neutron-Physical Calculations of the BN-800 Reactor in a Stationary Regime

Atomic Energy, 2015
The GEFEST800 software-hardware system was developed for performing real-time neutron-physical calculations of the BN-800 sodium-cooled fast reactor, viz. calculations of the effective breeding ratio, maximum reactivity excess, effi ciency of single and groups of control rods, total, specifi c, and linear density of power release in fuel assemblies ...
D. S. Asatryan, A. A. Belov, V. I. Belousov, V. P. Bereznev, D. V. Ivchenko, E. F. Seleznev, I. S. Chernova, V. N. Koshcheev, G. N. Manturov, A. A. Peregudov, M. Yu. Semenov, A. M. Tsibulya, Yu. Yu. Drobyshev, S. A. Karpov, I. V. Fedorov   +14 more
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