Buchumschlag

Loss of Stability and Possible Bending Shape of WWER1000 Fuel Assemblies Guide Tubes

Gespeichert in:

Bibliographische Detailangaben
Datum:	2015
Hauptverfasser:	A. V. Efimov, M. V. Maksimov, Ju. V. Romashov
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	2015
Schriftenreihe:	Nuclear and Radiation Safety (Scientific and technical journa)
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0000487099
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

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

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

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

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

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;
von: V. I. Skalozubov, et al.
Veröffentlicht: (2020)

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

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

Safe Transportation of Nuclear Fuel Assemblies by Means of Wheeled Robotic Platforms
von: S. Alyokhina, et al.
Veröffentlicht: (2021)

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

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)

Mathematical Models for Investigation of WWER¬1000/320 Transients
von: E. N. Nikulina, 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)

Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics
von: V. V. Halchenko, et al.
Veröffentlicht: (2016)

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

Effectiveness analysis management guide severe accidents on WWER based on lessons Fukushima accident
von: V. I. Skalozubov, et al.
Veröffentlicht: (2015)

Theory of VVER-1000 fuel rearrangement optimization taking into account both fuel cladding durability and burnup
von: Pelykh, S.N., et al.
Veröffentlicht: (2013)

Mathematical modeling of residual stresses in WWER-1000 elements after heat treatment
von: O. V. Makhnenko, et al.
Veröffentlicht: (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;
von: V. I. Borysenko
Veröffentlicht: (2020)

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

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

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)

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

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)

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)

Aerodynamic optimization of the shape of supersonic compressor stage guide blades
von: Ju. A. Kvasha, et al.
Veröffentlicht: (2017)

Bending Vibrations of the Bimorph Pirzoceramic Plates of Non-Canonical Shape
von: Shakeri Mobarake, et al.
Veröffentlicht: (2019)

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

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

Method for adaptation of WWER &quot;non-design” nuclear fuel in emergency operation
von: V. I. Skalozubov, et al.
Veröffentlicht: (2015)

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)

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

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)

ESTIMATION OF HEAT LOSSES FOR THE TUBE HEAT RECEIVER OF THE SOLAR TROUGH MODULES
von: Knysh, L.
Veröffentlicht: (2020)

Estimation of heat losses for the tube heat receiver of the solar trough modules
von: L. I. Knysh
Veröffentlicht: (2020)

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)

Adaptation of Accident Modelling of &quot;Not Design” for WWERs Nuclear Fuel Based on Criterion Method
von: A. D. Berezovskij, et al.
Veröffentlicht: (2015)

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)