Results 11 to 20 of about 302 (158)
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library
Science and Technology of Nuclear Installations, 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.
Sonia M. Reda +3 more
doaj +2 more sources
Investigation of the impact of steady-state VVER-1000 (1200) core characteristics on the reactor stability with respect to xenon oscillations [PDF]
Nuclear Energy and Technology, 2020 The article presents a method for obtaining an analytical expression for the criterion of stability of a VVER-1000 (1200) reactor with respect to xenon oscillations of the local power in the core, containing an explicit dependence of the criterion ratio ...
Rashdan Talal Al Malkawi +2 more
doaj +3 more sources
Comparative investigation of temperature reactivity feedback coefficients in a pressurized water reactor (PWR) with Alumina (Al2O3) and Titania (TiO2) nano-fluids as coolant [PDF]
مجله علوم و فنون هستهای, 2021 In the present work, using different volume percentages and different sizes of TiO2 (Titania) and Al2O3 (Alumina) nanoparticles, the important and essential parameters of VVER-1000 reactor, including dynamic parameters of the reactor (such as temperature
R. Kianpour, G.R. Ansarifar
doaj +1 more source
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 This paper introduces the utilization of the International Atomic Energy Agency’s toolkit for reactor technology assessment (RTA) application to deploy small modular reactors (SMRs) in the Czech Republic, Egypt, and Poland. The increasing demand for clean energy has led to the prominence of small modular reactors (SMRs) in addressing global energy ...
Waad Saleh +4 more
wiley +1 more source
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 In‐vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants. The most influential issues on the IVR strategy are in‐vessel core melt evolution, the heat fluxes imposed on the lower head, and the external cooling of reactor pressurized vessel (RPV).
Shilei Han +4 more
wiley +1 more source
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 +1 more source
Uranium Recovery from Phosphates for Self‐Sufficient Nuclear Power in the Eastern Mediterranean
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 Production of phosphate fertilizers (PF), without uranium recovery, amounts to dispersing uranium compounds on agricultural fields. These compounds are naturally hidden in phosphate rock deposits prior to processing. Such a dispersion is a cumulative environmental damage, that may become rather catastrophic in few hundred years, under the current rates
Nassar H. S. Haidar, Guglielmo Lomonaco
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 A typical 1100 MWe pressurized water reactor (PWR) is a second unit installed at the coastal site of Pakistan. In this paper, verification analysis of reactivity control worth by means of rod cluster control assemblies (RCCAs) for startup and operational conditions of this typical nuclear power plant (CNPP) has been performed.
Izza Shahid +9 more
wiley +1 more source
Mathematical Problems in Engineering, Volume 2022, Issue 1, 2022., 2022 The behavior of hybrid nanofluid and stagnation point flow toward a stretched surface along with melting heat transfer, second‐order slip, electric field, and magnetic field effect is investigated in this study. Hybrid nanoparticles alumina (Al2O3) and copper (Cu) are considered with the base fluids water (H2O).
Muhammad Jawad +4 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 A methodology for segmenting large metal components from nuclear power plants has been developed with a view to minimizing the number of containers to emplace segmented pieces. Spherocylinder‐type and rectangular prism‐type objects are modeled in shapes, and equations to calculate heights, widths, lengths, or angles for segmentation and the number of ...
Jae Min Lee +3 more
wiley +1 more source