Cover Image

Comparative Analysis of Isotopic Composition of VVER-1000 Westinghouse and TVEL Spent Fuel

Saved in:

Bibliographic Details
Date:	2016
Main Author:	Ju. P. Kovbasenko
Format:	Article
Language:	English
Published:	2016
Series:	Nuclear and Radiation Safety (Scientific and technical journa)
Online Access:	http://jnas.nbuv.gov.ua/article/UJRN-0000597588
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

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)

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

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

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)

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

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

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

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)

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

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)

Overview of General Aspects in Using Different Types of Fuel Assemblies in VVER-1000 Mixed Fuel Loadings
by: V. B. Krytskyi, et al.
Published: (2016)

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

Comparative analysis of methodological approaches to the calculational determination of the forces acting on the VVER-1000 reactor support elements
by: V. O. Posokh, et al.
Published: (2020)

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)

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)

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

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)

Development and Validation of VVER-1000 Thermohydraulic Computer Model for TRACE Computer Code
by: S. E. Janovskij, et al.
Published: (2017)

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

Modeling and analysis of radionuclide structure of high active waste from VVER-440 reactors spent nuclear fuel reprocessed with Production Association &quot;Mayak&quot; Technology
by: P. M. Rusinko, et al.
Published: (2019)

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

Analysis of SG Feeding by Mobile Pump under Total Blackout of NPP with VVER-1000/320
by: M. P. Vyshemirskij, et al.
Published: (2016)

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

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

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

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

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

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

Vulnerability Analysis of Pipelines and Equipment of the Existing NPP Power Units with VVER-1000 under Vibrations Caused by the Aircraft Crash
by: L. B. Shamis, et al.
Published: (2017)

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)

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

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

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)

Comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi &quot;Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000&quot;
by: V. I. Borysenko
Published: (2020)

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

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

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

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