Results 11 to 20 of about 705,564 (243)
Расчет градиента температуры перспективного ядерного топлива для реактора типа ВВЭР [PDF]
, 2015 The paper considers the possibility of using the dispersion of fuel in VVER-1000 reactors.
Чуйкина, Анастасия Владимировна +1 more
core +2 more sources
Possible in-service damages of steam generators at VVER-1000 and VVER-1200 NPP units and their impact on long-term operation [PDF]
E3S Web of Conferences, 2020 Specific features of corrosion-mechanical damages of primary circuit header to steam generator vessel branch welds at VVER-1000 NPPs and their impact on safety and economic efficiency during long-term operation are analysed. Measures to avoid the damages
Arzhaev Alexander +10 more
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
Наближена оцінка температурного стану керамічного ядерного палива в циліндричних твелах та впливу на нього процесів і параметрів конструкцій активної зони реактора [PDF]
, 2008 The approximate mathematical model of the temperature state of ceramic nuclear fuels in cylindrical fuel elements was proposed in the form of linear ordinary differential equation and the boundary conditions. The theory of heat conduction and assumptions
Chibisov, Dmytro, Romashov, Yury
core +2 more sources
3-D COUPLED SIMULATION OF A VVER 1000 WITH PARCS/ATHLET [PDF]
EPJ Web of Conferences, 2021 A new OECD/NEA benchmark entitled “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster” is starting. This benchmark, based on high quality measurements performed at the NPP Rostov Unit 2, aims to validate and assess ...
Henry Romain +3 more
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
Selection of a turbulence model to calculate the temperature profile near the surface of VVER-1000 fuel assemblies in the NPP spent fuel pool [PDF]
Nuclear Energy and Technology, 2021 The paper considers the problem of selecting a turbulence model to simulate natural convection near the surface of a VVER-1000 fuel assembly unloaded from the reactor by computational fluid dynamics (CFD simulation) methods.
Aleksandra V. Voronina, Sergey V. Pavlov
doaj +3 more sources
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