Prediction of the maximum temperature inside container with spent nuclear fuel

Prediction of the maximum temperature inside container with spent nuclear fuel

Gespeichert in:

Bibliographische Detailangaben
Datum:	2018
Hauptverfasser:	S. V. Alokhina, O. M. Dybach, A. O. Kostikov, D. O. Dimitriieva
Format:	Artikel
Sprache:	English
Veröffentlicht:	2018
Schriftenreihe:	Nuclear and Radiation Safety (Scientific and technical journa)
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0000905559
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

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

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

Safety issues of the dry storage of the spent nuclear fuel
von: Alyokhina, S., et al.
Veröffentlicht: (2017)

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

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

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

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

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)

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

Scientific basis of thermal safety analysis of dry storage of spent nuclear fuel on zaporizhska NPP
von: Alyokhina, S., et al.
Veröffentlicht: (2020)

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)

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)

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

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

Area dose distribution predictive estimate from a nearby territory at building of centralized storage facility for spent nuclear fuel
von: L. I. Pavlovskyi, et al.
Veröffentlicht: (2016)

Multiple recycle fuel cycle for spent nuclear fuel components incineration in fusion-fission hybrid
von: Moiseenko, V.Е., et al.
Veröffentlicht: (2022)

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

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)

The state of fuel-containing materials inside the NSC "Arka" and problems which connected with the ensuring of their nuclear and radiation safety
von: V. O. Krasnov, et al.
Veröffentlicht: (2019)

Prospects of managing Ukrainian VVER-1000 spent nuclear fuel and products of its reprocessing
von: V. M. Vasylchenko, et al.
Veröffentlicht: (2013)

Deep reprocessing of spent nuclear fuel as a key step for sustainable development of nuclear energy
von: B. H. Shabalin, et al.
Veröffentlicht: (2016)

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)

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

Amplitude of vortical turbulence in crossed fields in separator of spent nuclear fuel at optimum parameters
von: Levchuk, I.P., et al.
Veröffentlicht: (2016)

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)

Delving into some specific features of the magnetic systems used for the plasma recycling of the spent nuclear fuel (SNF)
von: Yuferov, V.B., et al.
Veröffentlicht: (2022)

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)

Calculations of the nuclide composition of spent nuclear fuel RBMK-1000 for verification computer module SCALE-6
von: V. V. Solovev, et al.
Veröffentlicht: (2013)

Comparative analysis of numerical methods used for thermal modeling of spent nuclear fuel dry storage systems
von: Alyokhina, S., et al.
Veröffentlicht: (2019)

Assessment of radiation impact on the environment components while preparing for construction site of centralized storage facility for spent nuclear fuel (CSSNF)
von: L. I. Pavlovskyi, et al.
Veröffentlicht: (2016)

Mathematical dependence for the 137Cs concentration in spent nuclear fuel and its using for experimental data processing
von: V. V. Halchenko, et al.
Veröffentlicht: (2013)

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

Method for assessment of residual heat generation within preparation of spent nuclear fuel shipment from research reactors
von: S. H. Kadalev
Veröffentlicht: (2018)

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, S.V.
Veröffentlicht: (2018)

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

The main positions of the "Concept for managing spent nuclear fuel of VVER-1000 and products of its reprocessing which are to be returned to Ukraine"
von: V. M. Vasylchenko, et al.
Veröffentlicht: (2014)