Cover Image

Area dose distribution predictive estimate from a nearby territory at building of centralized storage facility for spent nuclear fuel

Saved in:

Bibliographic Details
Date:	2016
Main Authors:	L. I. Pavlovskyi, P. O. Bakhmachuk, O. I. Stoianov
Format:	Article
Language:	English
Published:	2016
Series:	Problems of nuclear power plants safety and of Chornobyl
Online Access:	http://jnas.nbuv.gov.ua/article/UJRN-0000711990
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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Dispersion fuel for nuclear research facilities
by: Kushtym, А.V., et al.
Published: (2017)

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

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

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

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

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

Aerial Infrared Monitoring for Nuclear Fuel Cycle Facilities in Ukraine
by: S. A. Stankevych, et al.
Published: (2015)

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

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

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

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

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

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

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

The formation of complex chemical compounds in the spent fuel and their influence on separation processes
by: Yuferov, V.B., et al.
Published: (2017)

Effect of locking the bend of waveguide nearby critical frequencies of the second mode
by: V. L. Pazynin
Published: (2017)

Comparative Analysis of Isotopic Composition of VVER-1000 Westinghouse and TVEL Spent Fuel
by: Ju. P. Kovbasenko
Published: (2016)

Application of automatic orbital welding in manufacture of absorbing inserts of containers for used nuclear fuel storage
by: V. A. Bogdanovskij, et al.
Published: (2011)

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

Assessment of radioecological capacity of the territories under the impact of nuclear fuel cycle objects
by: I. P. Drozd, et al.
Published: (2017)

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