Buchumschlag

Radiation tests of products made of calcium-thermal zirconium grade STZ-110 under operation of the VVER-440 reactor

Gespeichert in:

Bibliographische Detailangaben
Datum:	2020
Hauptverfasser:	A. P. Mukhachev, O. A. Kharytonova, T. A. Evdokimova
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	2020
Schriftenreihe:	Nuclear physics and atomic energy
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0001221203
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

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

Resource-saving and environmental protection in nuclear-grade zirconium and hafnium production
von: A. P. Mukhachev, et al.
Veröffentlicht: (2023)

Electrode processes in electrolysis of zirconium at production of plastic zirconium for nuclear energy
von: Mukhachev, A.P., et al.
Veröffentlicht: (2019)

Simulation of two-phase flow on shell side of VVER-440 secondary boilers
von: Gergely, K., et al.
Veröffentlicht: (2009)

Justification of equivalence criteria for high-level waste from VVER-440 spent fuel reprocessing
von: A. N. Masko, et al.
Veröffentlicht: (2013)

Radiation-Induced Embrittlement of WWER-440 Reactor Pressure Vessel Steel under Loading
von: Grinik, E.U., et al.
Veröffentlicht: (2003)

Solubility of calcium oxide and zirconium dioxide in eutectic of calcium chloride and alkali metal chloride
von: L. V. Hrytsai, et al.
Veröffentlicht: (2015)

Zirconium Concentrate Autoclave Decomposition at the Presence of Calcium Fluoride
von: T. V. Pavlenko, et al.
Veröffentlicht: (2010)

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

Balance evaluation for the formation of vitrified high level waste at VVER-440 Rivne NPP spent fuel reprocessing
von: Ju. A. Olkhovik
Veröffentlicht: (2014)

Electrochemical reduction of zirconium dioxide in calcium oxide and chloride melts
von: L. V. Hrytsai, et al.
Veröffentlicht: (2015)

Modeling and analysis of radionuclide structure of high active waste from VVER-440 reactors spent nuclear fuel reprocessed with Production Association &quot;Mayak&quot; Technology
von: P. M. Rusinko, et al.
Veröffentlicht: (2019)

The influence of distribution of carbides wear on 110Kh18M-ShD (440S) steel
von: O. A. Hlotka, et al.
Veröffentlicht: (2017)

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

Current physical problems of the dynamic damage in elements of the first circuit of VVER reactors
von: I. H. Sharaievskyi, et al.
Veröffentlicht: (2022)

COMPOSITES OF CALCIUM PHOSPHATE AND ZIRCONIUM DIOXIDE AS BIOCOMPATIBLE COATINGS OF METAL IMPLANTS
von: Zatovsky, Іgor, et al.
Veröffentlicht: (2024)

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

Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel
von: Schuhknecht, J., et al.
Veröffentlicht: (2010)

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

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

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)

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)

Кременчуку — 440 років
Veröffentlicht: (2011)

Nuclear zirconium – the basis of alloys with improved neutron-physical, radiation, and corrosion properties
von: Mukhachev, A.P., et al.
Veröffentlicht: (2020)

The influence of surface treatment of tubes for fuel from zirconium Zr1Nb and E110 alloys
von: I. A. Petelguzov, et al.
Veröffentlicht: (2016)

Properties of high-strength titanium alloy T110 joints made by fusion welding
von: S. V. Akhonin, et al.
Veröffentlicht: (2014)

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)

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)

Numerical Analysis of the Stress State of Near-Circular Hollow Cylinders Made of Functionally Graded Materials
von: Рожок, Л. С.
Veröffentlicht: (2024)

Numerical Analysis of the Stress State of Near-Circular Hollow Cylinders Made of Functionally Graded Materials
von: Рожок, Л. С.
Veröffentlicht: (2024)

Fatigue resistance of welded elements of freight cars of a new design made from steels of S345 and S390 grade
von: A. G. Rejdemejster, et al.
Veröffentlicht: (2018)

Reliability test of generator thermopiles made with the use of arc plasma spraying method
von: A. V. Simkin, 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)

HEAT TESTS OF POWER CABLES WITH XLPE INSULATION AT DIRECT VOLTAGES UP TO 110 KV
von: Antonets, T. Yu., et al.
Veröffentlicht: (2015)

Finding of interdependence between yield of native copper concentrate made of basalt input and electric field intensity and size grades
von: V. P. Nadutyj, et al.
Veröffentlicht: (2015)

Effects of Pistacia atlantica resin oil on the level of VEGF, hydroxyproline, antioxidant and wound healing activity in STZ-induced diabetic rats
von: B. Shahouzehi, et al.
Veröffentlicht: (2018)

Westinghouse Fuel Cladding Corrosion Resistance under Operation in the Conditions of VVER-1000 Primary Water Chemistry. Determination of the Corrosion Activation Energy for Zirconium Alloy and Verification of the Computer Model
von: V. A. Zuiok, et al.
Veröffentlicht: (2023)

Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor
von: Azhazha, V.M., et al.
Veröffentlicht: (2005)

The role of calcium uniporter in calcium-homeostasis of the exorbital lacrimal gland secretory cells
von: A. B. Kotliarova, et al.
Veröffentlicht: (2014)