Problems of abnormal dynamics of thermal hydraulic processes in prospective reactors with supercritical parameters of light water coolant

Problems of abnormal dynamics of thermal hydraulic processes in prospective reactors with supercritical parameters of light water coolant

Gespeichert in:

Bibliographische Detailangaben
Datum:	2021
Hauptverfasser:	I. H. Sharaievskyi, N. M. Fialko, A. V. Nosovskyi, L. B. Zimin, T. S. Vlasenko, H. I. Sharaievskyi
Format:	Artikel
Sprache:	English
Veröffentlicht:	2021
Schriftenreihe:	Nuclear power and the environment
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0001403458
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

Main directions of Russian development of prospective structures of water-cooled supercritical pressure reactors
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2020)

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

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)

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

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

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

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)

Thermal hydraulic calculations of the WWR-SM research reactor
von: S. A. Baytelesov, et al.
Veröffentlicht: (2020)

Thermal hydraulic method of optimizing the thermal resistance of nuclear fuel of reactor installations
von: V. I. Skalozubov, et al.
Veröffentlicht: (2024)

Problems of the thermal-hydraulic computer codes perfection
von: I. G. Sharaevskij, et al.
Veröffentlicht: (2015)

Improvement of Reliability and Ecological Safety of NPP Reactor Coolant Pump Seals
von: S. Shevchenko, et al.
Veröffentlicht: (2020)

Study of Heat Transfer Processes in Modelled Core of Nuclear Reactor with Helium Coolant
von: A. A. Avramenko, et al.
Veröffentlicht: (2017)

Electron irradiation, temperature, and stress effect on corrosion of Zr-, Ni-Cr-, and Fe-Cr-based alloys in the vicinity of the water coolant supercritical transition
von: Bakai, O.S., et al.
Veröffentlicht: (2020)

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)

Comparison of statistical properties of coolant temperature and neutron flux in a reactor PWR-1000
von: A. D. Skorbun, et al.
Veröffentlicht: (2017)

Effect of permeability of peble bed on heat transfer in the core of nuclear reactor with helium coolant
von: A. A. Avramenko, et al.
Veröffentlicht: (2017)

Physical substantiation of the mechanical sealing systems automatic diagnostics problem of NPP coolant reactor pumps
von: A. V. Nosovskij, et al.
Veröffentlicht: (2019)

Computational dosimetry and post-irradiation studies of the electron beam irradiation-assisted corrosion and stress corrosion cracking of statically strained steel samples in a supercritical water coolant
von: Bakai, O.S., et al.
Veröffentlicht: (2022)

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

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

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

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)

Self-sustained regime of nuclear burning wave in U–Pu fast reactor with Pb–Bi coolant
von: Fomin, S.P., et al.
Veröffentlicht: (2007)

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

Методологія визначення режиму початку кипіння в тепловидільних збірках твелів шляхом аналізу акустичного шуму
von: Sharaievskyi, G.
Veröffentlicht: (2016)

Method for adaptation of initial conditions of thermoacoustic coolant instability in "wave" reactor core problems of Shornobyl
von: V. I. Skalozubov, et al.
Veröffentlicht: (2015)

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)

Identification of parameters of the model of thermal and hydraulic processes in the crossflow heat exchanger, based on the analogy between thermal and hydraulic resistances
von: S. D. Vinnichuk, et al.
Veröffentlicht: (2018)

Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant circuit of WWER-1000 reactor
von: Yu. V. Fylonych, et al.
Veröffentlicht: (2021)

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

Thermal hydraulics verification safety studies to support the licensing of neutron source Accelerator Driven System
von: O. V. Kukhotskyi, et al.
Veröffentlicht: (2020)

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

Thermal-Hydraulic Safety Analysis of Mixed Core Loads for Ukrainian NPPs with VVER-1000
von: Yu. Yu. Vorobiov, et al.
Veröffentlicht: (2016)

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)

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