Results 11 to 20 of about 375 (173)
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
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
Ultrasonic monitoring of the VVER-1000 FA form change
Nuclear Energy and Technology, 2022 A procedure has been developed to determine the geometrical parameters of fuel assemblies (FA) by an ultrasonic pulse-echo technique used for all types of light-water reactor FAs. The measurement of geometrical parameters is achieved through the pairwise installation of ultrasonic transducers opposite the FA spacer grid faces at a distance of not more ...
Voronina,Aleksandra +2 more
openaire +3 more sources
Multiple usage of thorium-based fuel in a VVER-1000 reactor
Nuclear Energy and Technology, 2022 This paper considers the use of unconventional fuel in nuclear power reactors, using the example of a VVER-type unit, in order to find out the possibility of saving natural fissile uranium nuclei. Saving fissile uranium is one of the important tasks, the solution of which will give time for the development of a two-component nuclear power industry that
Kazansky,Yury +2 more
openaire +3 more sources
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
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
Automated system for control of VVER-1000 fuel properties considering fuel cladding damage parameter. [PDF]
Trudy Odesskogo Politehničeskogo Universiteta, 2018 An automated system for control of VVER-1000 reactor fuel properties considering fuel element cladding damage parameter, fuel burnup and axial offset has been proposed.
Pelykh S. +3 more
doaj +3 more sources