Cover Image

Comprehensive diagnostic monitoring of inner defects in welded joint of the assembly connecting collector to steam generator housing in WWER-1000 power unit

Saved in:

Bibliographic Details
Date:	2016
Main Authors:	L. S. Ozhigov, A. S. Mitrofanov, G. D. Tolstolutskaja, E. A. Krajnjuk, S. V. Shramchenko
Format:	Article
Language:	English
Published:	2016
Series:	Technical diagnostics and non-destructive testing
Online Access:	http://jnas.nbuv.gov.ua/article/UJRN-0000927706
Tags:	Add Tag No Tags, Be the first to tag this record!
Journal Title:	Library portal of National Academy of Sciences of Ukraine \| LibNAS

Institution

Library portal of National Academy of Sciences of Ukraine | LibNAS

Similar Items

Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
by: V. I. Skalozubov, et al.
Published: (2019)

Loss of Stability and Possible Bending Shape of WWER1000 Fuel Assemblies Guide Tubes
by: A. V. Efimov, et al.
Published: (2015)

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

Corrosion of the second-circuit NPP blocks with WWR-1000
by: L. S. Ozhigov, et al.
Published: (2016)

Determination of Stiffness Characteristics for WWER-1000 Support Components
by: V. M. Vasylchenko, et al.
Published: (2019)

Mathematical Models for Investigation of WWER¬1000/320 Transients
by: E. N. Nikulina, et al.
Published: (2018)

An improved method for automated control of the WWER-1000 power maneuvering
by: Huiyu Zhou, et al.
Published: (2017)

Development of ultrasonic testing procedures and determination of performance of the assembly of the joint of header to steam generator PGV-1000M
by: A. V. Dub, et al.
Published: (2014)

An autonomous system of a spent fuel pool cooling in WWER-1000
by: Ihschenko, O.P.
Published: (2017)

Reply to V. I. Borysenko&#039;s comment on the article &quot;Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000&quot;
by: V. I. Skalozubov, et al.
Published: (2020)

Models and Methods for Automated Control of Power Change at WWER¬1000 Power Unit
by: T. Foshch, et al.
Published: (2018)

Mathematical modeling of residual stresses in WWER-1000 elements after heat treatment
by: O. V. Makhnenko, et al.
Published: (2021)

Research of WWER-1000 Power Change Modes for Operation in the Load-Following Mode
by: R. Glushenkov
Published: (2020)

COMBINATION OF PVT-COLLECTORS WITH USING OF CONTROLLED CONNECTIONS
by: Bondarenko, D.
Published: (2024)

Adaptation of Helios Models for WWER¬440 Fuel Assemblies for Application by the TRACE/PARCS Program
by: Yu. M. Ovdiienko, et al.
Published: (2019)

The Device for Burnup Control of RBMK-1000 Spent Fuel Assemblies
by: I. L. Zajtsevskij, et al.
Published: (2015)

Corrosion damages of pipelines at NNP and problems of their control
by: L. S. Ozhigov, et al.
Published: (2017)

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

Оptimization of power control program switching for a WWER-1000 under transient operating conditions
by: Huiyu Zhou, et al.
Published: (2018)

Calculation of Neutron Fluence and Energy Release in WWER¬1000 Structural Components Using Monte Carlo Method
by: A. M. Abdullaev, et al.
Published: (2018)

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

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

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

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

Evaluation of the possibility of further use of collectors of the primary steam superheaters with operating damages
by: V. I. Astashkin, et al.
Published: (2018)

On a product of the inner radii of symmetric multiply connected domains
by: Ja. V. Zabolotnyj, et al.
Published: (2017)

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

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

Strength Analysis of PGV-1000M Steam Generator Support
by: Ja. R. Dubik, et al.
Published: (2017)

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

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

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

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

Features of application of high-viscosity dampers to improve the seismic resistance of high-temperature filters in NPP with WWER-1000 reactors
by: V. V. Kirichok, et al.
Published: (2016)

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

Contact Interaction of Steam Turbine Inner Casing Elements During Plastic Deformation
by: Пальков, С. А., et al.
Published: (2021)

Contact Interaction of Steam Turbine Inner Casing Elements During Plastic Deformation
by: Пальков, С. А., et al.
Published: (2021)

Contact Interaction of Steam Turbine Inner Casing Elements During Plastic Deformation
by: S. A. Palkov, et al.
Published: (2021)

Comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi &quot;Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000&quot;
by: V. I. Borysenko
Published: (2020)

Overview of General Aspects in Using Different Types of Fuel Assemblies in VVER-1000 Mixed Fuel Loadings
by: V. B. Krytskyi, et al.
Published: (2016)