Buchumschlag

Metalophysical problems of WWER reactor vessel welding joints reliability

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-0001403555
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

Study of WWER reactors neutronic noise spectral images in irregular thermohydraulic regimes of core zones
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)

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)

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

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

Mathematical modeling of residual stresses in composite welded joints of WWER-1000 reactor vessel cover with CPS nozzles
von: A. A. Makarenko, et al.
Veröffentlicht: (2022)

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

Prediction of irradiation embrittlement in WWER-440 Reactor Pressure Vessel materials
von: Brumovsky, M., et al.
Veröffentlicht: (2007)

Lifetime Analysis of WWER Reactor Pressure Vessel Internals Concerning Material Degradation
von: Dudra, Ju., et al.
Veröffentlicht: (2010)

Estimation of the error of functionals calculation results of the neutron flux onto the WWER 1000 reactor pressure vessel
von: V. L. Demekhin, et al.
Veröffentlicht: (2013)

Estimation of the error of functionals calculation results of the neutron flux onto the WWER 1000 reactor pressure vessel
von: V. L. Demekhin, et al.
Veröffentlicht: (2012)

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)

Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness
von: V. M. Revka, et al.
Veröffentlicht: (2024)

The Use of Master Curve Method for Statistical Re-Evaluation of Surveillance Test Data for WWER-1000 Reactor Pressure Vessels
von: Revka, V.M., et al.
Veröffentlicht: (2010)

Impact of technological parameters of arc deposition of an anti-corrosion layer in the vessel of WWER-1000 reactor on residual stress distribution
von: O. V. Makhnenko, et al.
Veröffentlicht: (2020)

Validation of the code package MCPV adapted for neutron transport calculation within WWER-440 reactor near-vessel space
von: A. M. Pugach, et al.
Veröffentlicht: (2019)

A Data Scatter for a Shift of the Ductile to Brittle Transition Temperature for WWER¬1000 Reactor Pressure Vessel Materials
von: V. N. Revka
Veröffentlicht: (2018)

Neutron Embrittlement of WWER Reactors: EC-Supported Projects
von: Ahlstrand, R., et al.
Veröffentlicht: (2004)

Redistribution of residual welding stresses inside the inner-body shaft of the reactor WWER-1000 in the process of service
von: O. V. Makhnenko, et al.
Veröffentlicht: (2014)

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

On the issue of improving reliability of the welded joints in mining equipment
von: Ju. Makeev, et al.
Veröffentlicht: (2015)

Dimensioness method of assessing the conditions of thermal shock to the reactor vessel
von: V. I. Skalozubov, et al.
Veröffentlicht: (2014)

Analysis of criticality of melt during severe accidents in reactor vessel
von: Yu. P. Kovbasenko, et al.
Veröffentlicht: (2018)

Different approaches to estimation of reactor pressure vessel material embrittlement
von: V. M. Revka, et al.
Veröffentlicht: (2013)

Uncertainty determination of fast neutron fluence onto the WWER pressure vessel metal surveillance specimens
von: O. M. Puhach, et al.
Veröffentlicht: (2021)

Criteria of thermochemical conditions of steam gas explosions in dynamic accident modes at nuclear power units with WWER reactors
von: V. M. Vashchenko, et al.
Veröffentlicht: (2022)

Criteria of thermochemical conditions of steam gas explosions in dynamic accident modes at nuclear power units with WWER reactors
von: Vashchenko, Volodymyr M., et al.
Veröffentlicht: (2022)

Technological capabilities of improving the reliability of welded joints of aluminium-lithium alloys
von: T. M. Labur
Veröffentlicht: (2011)

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)

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

Effect of alternating magnetic field on magnetic properties, structure and stressed state of vessel steel welded joints
von: K. A. Jushchenko, et al.
Veröffentlicht: (2017)

Analysis of Reliability¬Critical Hydraulic Impact Conditions at WWER¬1000 NPP Active Safety Systems
von: V. Skalozubov, et al.
Veröffentlicht: (2019)

Evaluation of serviceability of pipeline of the first contour of WWR-M reactor with defects in welded joints
von: O. V. Makhnenko, et al.
Veröffentlicht: (2015)

Reliability and cost-effectiveness of high-pressure vessels for technical gases, produced in Ukraine
von: E. F. Garf, et al.
Veröffentlicht: (2012)

Influence of residual process stresses on brittle fracture resistance of WWER-1000 reactor baffle in case of an emergency
von: O. V. Makhnenko, et al.
Veröffentlicht: (2022)

Models of WWER-1000 nuclear reactor with division into zones on verti-cal axis for information technology of control
von: V. P. Severin, et al.
Veröffentlicht: (2021)

Effect of residual stresses in welded joints of two-layer steels on in-service reliability of metal structures
von: V. V. Chigarev, et al.
Veröffentlicht: (2013)

Comprehensive diagnostic monitoring of inner defects in welded joint of the assembly connecting collector to steam generator housing in WWER-1000 power unit
von: L. S. Ozhigov, et al.
Veröffentlicht: (2016)

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

Radiation creep effect on the form change determination of WWER-1000 reactor core baffle under longterm operation
von: Yu. Chyrkov, et al.
Veröffentlicht: (2021)