Buchumschlag

Main directions of Russian development of prospective structures of water-cooled supercritical pressure reactors

Gespeichert in:

Bibliographische Detailangaben
Datum:	2020
Hauptverfasser:	I. H. Sharaievskyi, N. M. Fialko, A. V. Nosovskyi, L. B. Zimin, T. S. Vlasenko, H. I. Sharaievskyi
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	2020
Schriftenreihe:	Nuclear power and the environment
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0001186383
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!
Назва журналу:	Library portal of National Academy of Sciences of Ukraine \| LibNAS

Institution

Library portal of National Academy of Sciences of Ukraine | LibNAS

Ähnliche Einträge

Problems of abnormal dynamics of thermal hydraulic processes in prospective reactors with supercritical parameters of light water coolant
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2021)

World trends of construction development of water-cooled supercritical pressure reactors
von: I. H. Sharaevskyi, et al.
Veröffentlicht: (2020)

Prospective directions of increasing operating reliability and providing operational management of the npp main equipment resources
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2021)

Evolution of thermophysical problems in constructions of VVVR reactors main circulation pumps
von: H. I. Sharaievskyi, et al.
Veröffentlicht: (2019)

Metalophysical problems of WWER reactor vessel welding joints reliability
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2022)

Current physical problems of the dynamic damage in elements of the first circuit of VVER reactors
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2022)

Study of WWER reactors neutronic noise spectral images in irregular thermohydraulic regimes of core zones
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2022)

Specifics of the flow of supercritical water under conditions of mixed convection
von: N. M. Fialko, et al.
Veröffentlicht: (2018)

Mathematical model of automatic recognition of latent pre-emergency conditions of shaft mechanical sealing systems of NPP main circulation pumps
von: A. V. Nosovskyi, et al.
Veröffentlicht: (2020)

Problems of calculation of heat transfer crisis in fuel assembles of water cooled reactors
von: G. I. Sharaevskij, et al.
Veröffentlicht: (2018)

Heat transfer of supercritical pressure water in fuel assemblies in unsteady regime
von: A. A. Avramenko, et al.
Veröffentlicht: (2016)

Electron irradiation of the material samples of new generation nuclear reactors in the supercritical water convection loop
von: Bakai, A.S., et al.
Veröffentlicht: (2013)

Problems of the emergency thermal load calculation in the channels of the water-cooled nuclear reactors
von: G. I. Sharaevskij
Veröffentlicht: (2018)

Efects of heat flux in the channel wall and water pressure on the characteristics of flow and heat transfer in bare tubes at supercritical parameters
von: N. M. Fialko, et al.
Veröffentlicht: (2016)

Problems of diagnostical ensuring of water-water energetic reactors&#039; vibroacoustic safety (Rart 2)
von: N. M. Fialko, et al.
Veröffentlicht: (2016)

Problems of diagnostical ensuring of water-water energetic reactors&#039; vibroacoustic safety (Part I)
von: N. M. Fialko, et al.
Veröffentlicht: (2015)

Catalytic Gasification of Aqueous Coal Suspension under Supercritical Pressure
von: R. V. Korzh, et al.
Veröffentlicht: (2012)

Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
von: Переверзев, Д. А., et al.
Veröffentlicht: (2016)

Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
von: Переверзев, Д. А., et al.
Veröffentlicht: (2016)

Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
von: D. A. Pereverzev, et al.
Veröffentlicht: (2011)

Effect of Axial Distribution of Gadolinium Burnable Poison in Advanced Pressurized Water Reactor Assembly
von: H. M. Saad, et al.
Veröffentlicht: (2019)

Supercritical water convection loop control system
von: Boriskin, V.N., et al.
Veröffentlicht: (2014)

Prospects for the Development and Use of Water-Cooled Fuel (Review)
von: A. S. Makarov
Veröffentlicht: (2018)

CFD modeling of heat transfer under flow of supercritical parameters water in vertical bare tubes
von: N. M. Fialko, et al.
Veröffentlicht: (2018)

Heat transfer of supercritical pressure flow in pipe with changing thermal load
von: A. A. Avramenko, et al.
Veröffentlicht: (2016)

Dispenser for water sampling from supercritical convection loop
von: Boriskin, V.N., et al.
Veröffentlicht: (2014)

Monitoring the flow rate of water in the supercritical convection loop
von: Bakai, A.S., et al.
Veröffentlicht: (2016)

Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding
von: Zuyok, V., et al.
Veröffentlicht: (2022)

Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety
von: M. I. Yossef, et al.
Veröffentlicht: (2016)

Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety
von: Youssef, M.I., et al.
Veröffentlicht: (2016)

Percolation line, response functions, and Voronoi polyhedra analysis in supercritical water
von: Škvor, J., et al.
Veröffentlicht: (2012)

Steam explosions at severe accidents in pressurized nuclear reactors
von: I. L. Kozlov
Veröffentlicht: (2014)

Directions of the development of nuclear power plants technologies. Part 1. Light-water reactors
von: Kovetskiy V.M., et al.
Veröffentlicht: (2006)

Regimes of irradiation by electrons of samples of materials in supercritical water convection loop
von: Bakai, A.S., et al.
Veröffentlicht: (2017)

Reactor Pressure Vessel and Internals Steels Irradiation Performed at the LVR-15 Research Reactor
von: Erben, Oldřich, et al.
Veröffentlicht: (2001)

The prospect on the use of Be mirrors in a fusion reactor with Be first wall
von: Bardamid, A.F., et al.
Veröffentlicht: (2003)

Directions of the development of nuclear power plant technology. Heavy water, liquid- metal and gas reactors
von: Kovetskiy, et al.
Veröffentlicht: (2006)

Optimization of the cooling mode of circulating water in atomizing cooling towers
von: Shraiber O.A., et al.
Veröffentlicht: (2007)

Features of diagnostics of unsupposed thermal, vibroacoustic and neutron processes in the first contour of nuclear reactors
von: I. G. Sharaevskij, et al.
Veröffentlicht: (2018)

Hafnium in nuclear power industry: the evolution of increasing of the economic indicators and the operation safety of pressurized water nuclear reactors
von: Shilyaev, B.A., et al.
Veröffentlicht: (2018)