Buchumschlag

Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine

An analytical review of modern researches into spent nuclear fuel (SNF) dry cask storage, or dry storage thermal processes is presented and problems of creating scientific and methodological foundations for SNF dry storage thermal safety are discussed. Подано аналітичний огляд сучасних досліджень те...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Veröffentlicht in:	Проблеми машинобудування
Datum:	2018
1. Verfasser:	Alyokhina, S.V.
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	Інстиут проблем машинобудування ім. А.М. Підгорного НАН України 2018
Schlagworte:	Aerohydrodynamics and heat-mass exchange
Online Zugang:	https://nasplib.isofts.kiev.ua/handle/123456789/158791
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!
Назва журналу:	Digital Library of Periodicals of National Academy of Sciences of Ukraine
Zitieren:	Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine / S.V. Alyokhina // Проблеми машинобудування. — 2018. — Т. 21, № 3. — С. 4-12. — Бібліогр.: 42 назв. — англ, укр.

Institution

Digital Library of Periodicals of National Academy of Sciences of Ukraine

Ähnliche Einträge

Analytical Method of Profiling Axial-Radial Compressor Impellers
von: Rusanov, A.V., et al.
Veröffentlicht: (2018)

Heat Transfer During Subcooled Boiling in Tubes (A Review)
von: Gakal, P.G., et al.
Veröffentlicht: (2019)

Method for the Optimal Design of Vacuum-Evaporative Heat Pumps
von: Kuznetsov, M.A., et al.
Veröffentlicht: (2019)

Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine
von: S. V. Alyokhina
Veröffentlicht: (2018)

Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine
von: Alyokhina, Svitlana V.
Veröffentlicht: (2018)

Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine
von: Alyokhina, Svitlana V.
Veröffentlicht: (2018)

Thermal Analysis of Vertical Dry Storage Cask for Nuclear Spent Fuel in Off-Normal Conditions
von: M. Makarenko, et al.
Veröffentlicht: (2022)

Solar radiation influence onto the spent nuclear fuel dry storage container
von: Alyokhina, S.V., et al.
Veröffentlicht: (2018)

Expirience of using the SCALE software package for substantiation of nuclear safety of dry storage of spent nuclear fuel
von: Chernitskiy, S.V., et al.
Veröffentlicht: (2017)

Spent nuclear fuel dry storage: status and current issues
von: Yatsenko, M.V., et al.
Veröffentlicht: (2019)

Thermal aspects of some accident conditions at the dry spent nuclear fuel storage in the ventilated containers
von: S. V. Alokhina
Veröffentlicht: (2018)

Nuclear and Radiation Safety of the Centralized Spent Fuel Storage Facility in Ukraine
von: O. V. Hryhorash, et al.
Veröffentlicht: (2017)

Scientific and technical aspects of creating spent nuclear fuel shipping and storage equipment
von: I. R. Shegelman, et al.
Veröffentlicht: (2013)

Optimization of the width of air cooling duct of spent fuel cask
von: S. V. Aljokhina, et al.
Veröffentlicht: (2011)

Methodology for Determining the Thermal and Thermal-Stress States of a Concrete Storage Container for Spent Nuclear Fuel for Assessment of Its Service Life
von: S. Alyokhina, et al.
Veröffentlicht: (2021)

Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
von: Rudychev, V.G., et al.
Veröffentlicht: (2020)

Experimental installation for the study of heat transfer in helium environment during dry storage of spent nuclear fuel
von: Yatsenko, M.V., et al.
Veröffentlicht: (2022)

ANALYSIS OF METHODS OF THERMAL TRANSFER INTENSIFICATION IN SOLAR COLLECTORS US-ING FREE HEAT TRANSFER FLUID CIRCULATION MODE
von: Golovko , V., et al.
Veröffentlicht: (2024)

Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety
von: M. I. Yossef, et al.
Veröffentlicht: (2016)

Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety
von: Youssef, M.I., et al.
Veröffentlicht: (2016)

Heat recovery of the waste gas boilers, in combined heat and mass transfer apparatus
von: Tuz V.E., et al.
Veröffentlicht: (2011)

Potential of spent nuclear fuel
von: A. V. Korolev, et al.
Veröffentlicht: (2015)

The magnetoplasma separation method of spent nuclear fuel
von: Yuferov, V.B., et al.
Veröffentlicht: (2017)

Usage of Optimization Geometric Design Methods for the Problems of the Spent Nuclear Fuel Safe Storage
von: A. M. Chuhai, et al.
Veröffentlicht: (2020)

Assessment of spent batteries streams in Ukraine
von: Ishchenko, Vitalii
Veröffentlicht: (2021)

Influence of eccentricity on heat transfer in borehole counterflow heat exchanger of tube-in-tube type
von: Бучко, А. В., et al.
Veröffentlicht: (2016)

Influence of eccentricity on heat transfer in borehole counterflow heat exchanger of tube-in-tube type
von: Бучко, А. В., et al.
Veröffentlicht: (2016)

Increasing the efficiency of industrial mazut-gas boilers
von: Tuz V.E., et al.
Veröffentlicht: (2011)

On the 25th anniversary from the foundation of the State Institution “Scientific Center for Aerospace Research at the Earth Institute of Geological Sciences of the National Academy of Sciences of Ukraine”
von: Lyalko, Vadim, et al.
Veröffentlicht: (2017)

INFLUENCE OF GROUNDWATER FILTRATION FLOW ON THE THERMAL EFFICIENCY OF UNDERGROUND HEAT EXCHANGER
von: Basok, B., et al.
Veröffentlicht: (2022)

Modern Methods of Radiochemical Reprocessing of Spent Nuclear Fuel
von: T. V. Maltseva, et al.
Veröffentlicht: (2019)

Automated system for determining the burnup of spent nuclear fuel
von: V. A. Mokritskij, et al.
Veröffentlicht: (2014)

The optimization of calculation time and statistical error for the radiation shielding properties simulation of containers for storage of spent nuclear fuel
von: M. I. Holiuk, et al.
Veröffentlicht: (2021)

Prediction of the maximum temperature inside container with spent nuclear fuel
von: S. V. Alokhina, et al.
Veröffentlicht: (2018)

Simulation of the radiation environment during spent nuclear fuel management
von: O. V. Balan, et al.
Veröffentlicht: (2021)

Grinding the spent nuclear fuel simulating materials for the magnetoplasma separation
von: Vinnikov, D.V., et al.
Veröffentlicht: (2016)

Safety Properties Assessment of the Container for Storage of Spent Sources of Ionizing Radiation
von: I. O. Poliakova
Veröffentlicht: (2013)

Study of Spent Fuel Behavior in Beyond Design-Basis Storage Period
von: V. V. Halchenko
Veröffentlicht: (2017)

Mantle heat flow in the territory of Ukraine
von: Gordienko, V.V., et al.
Veröffentlicht: (2025)

Spent Nuclear Fuel Transport: Problem State and Analysis of Modern Approaches
von: A. V. Nosovskyi, et al.
Veröffentlicht: (2018)