Buchumschlag

Current physical problems of the dynamic damage in elements of the first circuit of VVER reactors

Gespeichert in:

Bibliographische Detailangaben
Datum:	2022
Hauptverfasser:	I. H. Sharaievskyi, T. S. Vlasenko, L. B. Zimin, A. V. Nosovskyi, N. M. Fialko, H. I. Sharaievskyi
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	2022
Schriftenreihe:	Nuclear power and the environment
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0001403534
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)

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

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

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)

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)

Influence of geometrical parameters of the VVER-1000 reactor construction elements to internals irradiation conditions
von: A. M. Pugach, et al.
Veröffentlicht: (2015)

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

Spectral characteristics of vibroacoustical vibrations in the primary circuit of VVER-1000
von: E. I. Sharaevskaja
Veröffentlicht: (2016)

Comparative analysis of methodological approaches to the calculational determination of the forces acting on the VVER-1000 reactor support elements
von: V. O. Posokh, et al.
Veröffentlicht: (2020)

Actual problems of vibroacoustic diagnostics of the first circuit of water-water energetic reactors
von: E. I. Sharaevskaja
Veröffentlicht: (2015)

Thermophysical aspects of diagnosis systems improving for the NPP first circuit
von: A. V. Nosovskij, et al.
Veröffentlicht: (2018)

State and Prospects of Containment Tightness Tests for VVER-1000 Reactor Installations
von: V. P. Kravchenko, et al.
Veröffentlicht: (2023)

Methodological approaches to determining the forces acting on the VVER-1000 reactor support elements under power unit operating loads
von: B. O. Posokh
Veröffentlicht: (2020)

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)

Sorting of surveillance specimen halves relative to their location in the VVER-1000 reactor under irradiation
von: Yu. S. Hulchuk, et al.
Veröffentlicht: (2019)

The method of control of nuclear power plant with VVER–1000 reactor in maneuverable mode
von: M. V. Maksimov, et al.
Veröffentlicht: (2015)

Lateral expansion and impact toughness correlation of VVER-1000 reactor pressure vessel materials
von: O. V. Tryhubenko
Veröffentlicht: (2014)

A method for VVER fuel element cladding reliability prediction
von: S. N. Pelykh, et al.
Veröffentlicht: (2014)

Modeling of residual welding stresses, radiation swelling and stressed state of enclosure of the reactor VVER-1000 in the process of operation
von: O. V. Makhnenko, et al.
Veröffentlicht: (2016)

Mathematical simulation of microstructure phase transformations at welding heating by example corrosion resistant cladding of the reactor vessel VVER-1000
von: O. V. Makhnenko, et al.
Veröffentlicht: (2018)

Radiation tests of products made of calcium-thermal zirconium grade STZ-110 under operation of the VVER-440 reactor
von: A. P. Mukhachev, et al.
Veröffentlicht: (2020)

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

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

Effect of recycling for physical parameters of reactor-stellarator
von: Rudakov, V.A.
Veröffentlicht: (2018)

Model of the Formation Damaging Factors of Dual Circuit Evaporator Unit
von: V. A. Reznikov, et al.
Veröffentlicht: (2013)

A MATHEMATICAL MODEL OF THE ELECTRICAL ENGINEERING COMPLEX FOR DRIVE OF MAIN CIRCULATION PUMPS OF NUCLEAR REACTOR VVER-1000 OF NUCLEAR POWER PLANTS
von: Vasyliv, K. M., et al.
Veröffentlicht: (2019)

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

SINGLE-CIRCUIT AND DUAL-CIRCUIT HEAT PUMP SYSTEMS. INTERRELATION OF PHYSICAL PROCESSES AND EFFICIENCY
von: Goshovskyi, S., et al.
Veröffentlicht: (2019)

Single-circuit and dual-circuit heat pump systems. Interrelation of physical processes and efficiency
von: S. V. Goshovskij, et al.
Veröffentlicht: (2019)

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

LIMITATIONS OF CURRENT OF THE THREE-PHASE ACTIVE POWER FILTER IN THE CONDITIONS OF OVERLOAD AND SHORT CIRCUIT
von: Vlasenko, R. V., et al.
Veröffentlicht: (2018)

Analysis of the preconditions of SF6 circuit breakers&#039; damage in 750 kV electric networks
von: V. H. Kuznetsov, et al.
Veröffentlicht: (2017)

Improving the methods for estimating radiation swelling and progressive dimensional changes of the elements of VVER¬1000 internals
von: O. V. Makhnenko, et al.
Veröffentlicht: (2019)

Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000
von: V. I. Borysenko, et al.
Veröffentlicht: (2023)

Improving the accuracy of thermal power determination of VVER
von: V. I. Borysenko, et al.
Veröffentlicht: (2019)

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)

Computer modeling of deformation of the elements of operating power equipment elements with damages
von: B. D. Drobenko
Veröffentlicht: (2010)