Buchumschlag

The Device for Burnup Control of RBMK-1000 Spent Fuel Assemblies

Gespeichert in:

Bibliographische Detailangaben
Datum:	2015
Hauptverfasser:	I. L. Zajtsevskij, A. A. Kuchmagra, O. S. Molchanov, G. I. Odinokin, E. A. Lebedev, A. E. Novikov, V. V. Solovev
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	2015
Schriftenreihe:	Nuclear and Radiation Safety (Scientific and technical journa)
Online Zugang:	http://jnas.nbuv.gov.ua/article/UJRN-0000485230
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

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)

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

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

Model of reactivity accident of the RBMK-1000 reactor
von: V. I. Borysenko, et al.
Veröffentlicht: (2022)

Determination of conservative conditions of the model of reactivity accident at RBMK 1000
von: V. I. Borysenko, et al.
Veröffentlicht: (2022)

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

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)

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

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

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

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)

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

Loss of Stability and Possible Bending Shape of WWER1000 Fuel Assemblies Guide Tubes
von: A. V. Efimov, et al.
Veröffentlicht: (2015)

Model of Reactivity Accident of the RBMK-1000 of the Chornobyl NPP 4th Power Unit
von: V. I. Borysenko, et al.
Veröffentlicht: (2021)

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

Peculiarities of the preparation technology of samples for radionuclide activity determination in the material of fuel channel tubes of RBMK reactors
von: A. N. Berlizov, et al.
Veröffentlicht: (2013)

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)

Research of Neutron Characteristics of ChNPP RBMK 1000 in the Institute for Nuclear Research in Pre¬ and Post¬Emergency Period: Retrospective Analysis
von: V. A. Khalimonchuk, et al.
Veröffentlicht: (2016)

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

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

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

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

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

Burnup and radiation embrittlement of the U-Mo neutron source target
von: Borts, B.V., et al.
Veröffentlicht: (2022)

Estimation of the amount of burnup of particles of pulverized coal in the tuyere hearth
von: V. V. Kalinchak, et al.
Veröffentlicht: (2013)

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

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;
von: V. M. Vasylchenko, et al.
Veröffentlicht: (2014)

The formation of complex chemical compounds in the spent fuel and their influence on separation processes
von: Yuferov, V.B., 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)

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

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

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

Heat transfer of supercritical pressure water in fuel assemblies in unsteady regime
von: A. A. Avramenko, et al.
Veröffentlicht: (2016)

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

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

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)

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)

Specifics of supercritical parameters of a flow under non-uniform heating of the fuel assembly channel walls
von: A. A. Avramenko, et al.
Veröffentlicht: (2014)