Results 11 to 20 of about 675,221 (193)
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
doaj +7 more sources
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
doaj +5 more sources
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
doaj +4 more sources
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
doaj +2 more sources
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
doaj +3 more sources
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
doaj +2 more sources
EPJ Web of Conferences, 2016 The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system.
Voloschenko Andrey +3 more
doaj +3 more sources
In-service change in the flexural rigidity of the VVER-1000 fuel assemblies [PDF]
Nuclear Energy and Technology, 2016 In-service dimensional stability of the VVER-1000 reactor fuel assemblies (FA) depends to a great extent on their flexural rigidity. A decrease in the flexural rigidity in the process of the FA operation in the reactor may lead to such FA bowing as will ...
S.V. Pavlov
doaj +2 more sources
, 2018 The first print magazine from 1000 Words. 2018 marks the 10th anniversary of 1000 Words, and what better way to celebrate than to publish a special print annual?
Clark, Tim, 1000 Words
core +6 more sources
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
doaj +1 more source