Cover Image

Overview of General Aspects in Using Different Types of Fuel Assemblies in VVER-1000 Mixed Fuel Loadings

Saved in:

Bibliographic Details
Date:	2016
Main Authors:	V. B. Krytskyi, V. V. Mukha, A. V. Nosovskyi, T. V. Pidhaietskyi, O. S. Pohonets
Format:	Article
Language:	English
Published:	2016
Series:	Nuclear and Radiation Safety (Scientific and technical journa)
Online Access:	http://jnas.nbuv.gov.ua/article/UJRN-0000597587
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

Thermal-Hydraulic Safety Analysis of Mixed Core Loads for Ukrainian NPPs with VVER-1000
by: Yu. Yu. Vorobiov, et al.
Published: (2016)

Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics
by: V. V. Halchenko, et al.
Published: (2016)

Evaluation of the Applicability of Cladding Deformation Model for VVER-1000 Fuel
by: Ju. Ju. Vorobev, et al.
Published: (2015)

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

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

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

Some Characteristics of Hypothetic TVSA with Fuel Enriched beyond 5% for VVER-1000
by: E. I. Beloded, et al.
Published: (2016)

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

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

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

A method for VVER fuel element cladding reliability prediction
by: S. N. Pelykh, et al.
Published: (2014)

Application of RELAP5/MOD3.2 Cladding Deformation Model for VVER-1000 Fuel in Design-Basis Accident Analysis
by: Ju. Ju. Vorobev, et al.
Published: (2016)

Features of mixing diesel fuels
by: E. B. Shevchenko, et al.
Published: (2012)

Mixed fuel based on organic waste
by: D. A. Matviichuk, et al.
Published: (2018)

An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly
by: S. M. Pelykh, et al.
Published: (2016)

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)

The Method and Burning Device for Phasic Combustion of Gaseous and Liquid Fuels with Fuel and Air Prolonged Mixing
by: V. S. Pikashov, et al.
Published: (2012)

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

Computer Analysis of Thermomechanical State of Sealing Steel Lining for Containment of NPPs with VVER-1000/V-320 in Emergencies
by: O. V. Hondliakh, et al.
Published: (2017)

Safe Transportation of Nuclear Fuel Assemblies by Means of Wheeled Robotic Platforms
by: S. Alyokhina, et al.
Published: (2021)

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
by: V. A. Zuiok, et al.
Published: (2023)

VVER‑1000 power monitoring based on neutron detector signals
by: V. I. Borysenko, et al.
Published: (2019)

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

Engineering Margin in Calculations of Energy Release in VVER¬1000 Core
by: A. M. Abdullaev, et al.
Published: (2018)

Problems of calculation of heat transfer crisis in fuel assembles of water cooled reactors
by: G. I. Sharaevskij, et al.
Published: (2018)

Methodology for Determination of Initial Boiling Point in Fuel Assemblies by Acoustic Noise Analysis
by: G. I. Sharaevskij
Published: (2016)

Adaptation of Helios Models for WWER¬440 Fuel Assemblies for Application by the TRACE/PARCS Program
by: Yu. M. Ovdiienko, et al.
Published: (2019)

Reply to V. I. Borysenko&#039;s comment on the article &quot;Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000&quot;
by: V. I. Skalozubov, et al.
Published: (2020)

Calculation of radiation fields in the VVER 1000 concrete biological shield using Monte Carlo code Serpent
by: O. M. Khotiaintseva, et al.
Published: (2023)

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

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

Spectral characteristics of vibroacoustical vibrations in the primary circuit of VVER-1000
by: E. I. Sharaevskaja
Published: (2016)

Methodological approaches to determining the forces acting on the VVER-1000 reactor support elements under power unit operating loads
by: B. O. Posokh
Published: (2020)

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

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

The realities of the present and the prospects of the production of bioethanol as a component of mixed fuels
by: A. A. Dolinskyi, et al.
Published: (2019)

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

Mathematical and Computer Modeling of Convective Heat Transfer in Fuel Cartridges of Fuel Elements with Different Shapes and Packing of Rods
by: K. V. Maksymenko-Sheiko, et al.
Published: (2022)

Lateral expansion and impact toughness correlation of VVER-1000 reactor pressure vessel materials
by: O. V. Tryhubenko
Published: (2014)

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