Results 21 to 30 of about 311 (155)
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 An optimal long‐term electric power strategy for Saudi Arabia to adopt nuclear power was evaluated using the MESSAGE tool. Saudi Arabia is predicted to experience an electricity shortage by 2025 with the present energy system. This electricity shortage could be postponed until 2035 by rehabilitating the existing power plants. The MESSAGE model predicts
Shadwan M. M. Esmail +2 more
wiley +1 more source
Investigation of the small break conditions in the primary circuit of a VVER-1000 reactor* [PDF]
Nuclear Energy and Technology, 2019 Modes with violation of the reactor plant cooling conditions on the primary circuit side of a VVER reactor were simulated using the TRAC-PD2 and Open FOAM thermohydraulic codes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer’s Guide Version 1.6.
Belozerov,Vladimir +2 more
openaire +3 more sources
Neutronic Performance of the VVER‐1000 Reactor Using Thorium Fuel with ENDF Library
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 In this paper, neutronic calculations and the core analysis of the VVER‐1000 reactor were performed using MCNP6 code together with both ENDF/B‐VII.1 and ENDF/B‐VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER‐1000 reactor was discussed.
Sonia M. Reda +4 more
wiley +1 more source
Trudy Odesskogo Politehničeskogo Universiteta, 2022 Fukushima Daiichi accidents led to the worldwide update of the NPP safety requirements. Particular attention was paid to severe accidents both during the design of new NPP units and during the safety reassessment of existing ones.
Володимир Петрович Кравченко +1 more
doaj +5 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 +1 more source
A Possibility for Large-Scale Production of 238Pu in Light-Water Reactor VVER-1000
Journal of Nuclear Engineering, 2022 This paper considers the possibility for large-scale production of plutonium isotope 238Pu in the light-water nuclear power reactor VVER-1000. 238Pu is a unique source of long-term autonomous energy supply in various devices for remote regions of the ...
Anatoly N. Shmelev +5 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2010 The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
doaj +1 more source
EPJ Web of Conferences, 2016 A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation ...
Košťál Michal +8 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor operated by the Research Center Rez in the Czech Republic has been conducted with the MCS Monte Carlo code developed at the Computational Reactor Physics ...
Fathurrahman Setiawan +2 more
doaj +1 more source
Alexandria Engineering Journal, 2018 Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar +3 more
doaj +1 more source