Cover Image

Some Characteristics of Hypothetic TVSA with Fuel Enriched beyond 5% for VVER-1000

Saved in:

Bibliographic Details
Date:	2016
Main Authors:	E. I. Beloded, 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-0000597599
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

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

Evaluation of the Applicability of Cladding Deformation Model for VVER-1000 Fuel
by: Ju. Ju. Vorobev, 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)

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

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)

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)

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

Assessing Impact of Input Data Uncertainty on Nuclear Fuel Criticality Analysis Results
by: E. I. Beloded, et al.
Published: (2015)

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

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)

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

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)

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)

Method of Parametric Assignment of Input Data for Irradiation Swelling Calculation of VVER-1000 Internals
by: I. V. Mirzov, et al.
Published: (2016)

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

Sorting of surveillance specimen halves relative to their location in the VVER-1000 reactor under irradiation
by: Yu. S. Hulchuk, et al.
Published: (2019)

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

Influence of geometrical parameters of the VVER-1000 reactor construction elements to internals irradiation conditions
by: A. M. Pugach, et al.
Published: (2015)

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

Determination of VVER-1000 Thermal Power Based on Background Signals of Self-Powered Neutron Detectors
by: V. Borysenko, et al.
Published: (2019)

Improving the methods for estimating radiation swelling and progressive dimensional changes of the elements of VVER¬1000 internals
by: O. V. Makhnenko, et al.
Published: (2019)

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

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)

Solving the Problem of Finding Hypothetically Connected Objects by Means of Spatial Multi-Valued Structures
by: Chetverikov, G.G., et al.
Published: (2011)

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

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)

Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000
by: V. I. Borysenko, et al.
Published: (2023)

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)

Approaches to Safety Justification for Loading of VSC-VVER Containers in ZNPP DSFSF
by: Ya. V. Kostiushko, et al.
Published: (2019)

Beyond the Gaussian
by: Fujii, K.
Published: (2011)

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

Modeling of residual welding stresses, radiation swelling and stressed state of enclosure of the reactor VVER-1000 in the process of operation
by: O. V. Makhnenko, et al.
Published: (2016)

Comparison of Two Control Programs of the VVER-1000 Nuclear Power Unit Using Regression Data Mining Models
by: T. Foshch, et al.
Published: (2017)

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)

On the possibility of enrichment of solid fuel with a high ash content in an apparatus with fluidized bed
by: Yatsenko V.P.
Published: (2001)

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