Results 21 to 30 of about 1,019,583 (175)
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
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
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
Safety analyses of reactor VVER 1000
Energy Procedia, 2017 Abstract Department of Electrical Power Engineering, Faculty of Electrical Engineering and Communication, Brno University of Technology (BUT) is participating in research of safety analyses of nuclear power plants, especially nuclear power plants with VVER 1000 reactors.
Jitka Vojackova +2 more
openaire +1 more source
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
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
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