Accident Management in VVER-1000 [PDF]
Science and Technology of Nuclear Installations, 2008 The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose
F. D'Auria +4 more
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Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code [PDF]
Nuclear Energy and Technology, 2023 The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library.
Md Imtiaj Hossain +3 more
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Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent [PDF]
Ядерна фізика та енергетика, 2023 To calculate radiation fields in the concrete biological shield (CBS) of the VVER-1000 reactor in this work, we have developed and applied the Monte Carlo code Serpent simulation framework based on the variance reduction technique. We have quantified the
O. M. Khotiaintseva +5 more
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Evaluating machine learned nuclear data precision in full core nuclear reactor Monte Carlo neutronics and computational efficiency analyses [PDF]
Scientific ReportsThis study evaluates the novel machine learning based reduction of cross-sections and energy grid of continuous-energy nuclear data for one year full core Monte Carlo criticality and burn-up analysis using OpenMC.
Alexander Hashemi +2 more
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Estimation of material degradation of VVER-1000 baffle [PDF]
EPJ Web of Conferences, 2017 The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark.
Harutyunyan Davit +5 more
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VVER-1000 BENCHMARK INTERPRETATION WITH MONTE CARLO CODE MCS [PDF]
EPJ Web of Conferences, 2021 An interpretation of the NEA-1517/82 benchmark from the SINBAD shielding database has been conducted with the MCS Monte Carlo code developed at the Ulsan National Institute of Science and Technology (UNIST) and the ENDF/B-VII.1 nuclear data library.
Setiawan Fathurrahman +4 more
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Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000 [PDF]
Ядерна фізика та енергетика, 2023 The article presents the results of the numerical simulation of the signal formation process of the background wires of self-powered neutron detectors (SPND) under the action of gamma radiation in the VVER-1000 core using MCNP code. The validation of the
V. I. Borysenko, V. V. Goranchuk
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VVER-1000 reactor model using the Serpent 2 code for core power distribution calculation [PDF]
Ядерна фізика та енергетика, 2023 A VVER-1000 reactor model using the Monte Carlo Serpent 2 code for core power distribution calculation is presented. The core and zones located near to the core were modeled in detail, without simplification.
V. V. Ilkovych
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Глобальная ядерная безопасность, 2023 The paper considers the efficiency and possibility of implementing into the operational practice of VVER-1000 power units the campaign extension mode at the sliding pressure of the second circuit.
A. S. Grachev +2 more
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Computational benchmark for fuel assembly of VVER-1000 using the Monte Carlo Serpent code [PDF]
Nuclear Technology and Radiation Protection, 2018 The use of a new Monte Carlo Serpent code for the calculation of water-cooled reactors is presented and a calculation scheme of the fuel assembly for VVER-1000 reactors developed.
Galchenko Vitaliy V. +2 more
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