Results 41 to 50 of about 127,616,970 (139)
APPLICATION OF SIMULATORS IN THE STUDY OF PROCESSES OCCURRING IN WWER‑1000 NUCLEAR REACTORS [PDF]
, 2021 The paper considers the relevance of the WWER‑1000 Reactor Simulation program and the relevance of this program for developing new tasks based on it.В работе рассмотрена актуальность программы WWER‑1000 Reactor Simulation и ее востребованность для ...
Вольман, М. А. +3 more
core
Corrosion of alloy E635 in conditions of reactors WWER-1000 [PDF]
, 2012 Исследована коррозия оболочек твэлов из сплава Э635 после испытаний в реакторе МИР и штатной эксплуатации в течение 3 и 6 лет в реакторах ВВЭР-1000.
Новоселов, А.Е. +3 more
core +2 more sources
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented ...
M. Cherubini +4 more
wiley +1 more source
Brittle Fracture Probabilistic Assessment of WWER-1000 RPVs
Volume 3: Design and Analysis, 2014 This paper presents a methodology for brittle fracture probability assessment of WWER-1000 RPVs subjected to PTS. The main attention of the study is focused on the definition of the stochastic input data: fracture toughness, CTB, size and shape of the defects. Fracture toughness of RPV metal in the initial state is determined, separately
Igor Orynyak +4 more
openaire +2 more sources
International Standard Problems and Small Break Loss‐of‐Coolant Accident (SBLOCA)
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 Best‐estimate thermal‐hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test ...
N. Aksan, Cesare Frepoli
wiley +1 more source
An automated boron management system for WWER-1000 nuclear reactors
Trudy Odesskogo Politehničeskogo Universiteta, 2014 The article is devoted to the problem of creating a system of automated control with boron regulation for reactor WWER-1000 series. Using the boron regulation to control WWER-1000 allows to extend its maximum output operation period, ensuring the ...
Таїсія Олександрівна Цисельська +1 more
doaj +4 more sources
Determination of Stiffness Characteristics for WWER-1000 Support Components
Nuclear and Radiation Safety, 2019 Available approaches to computer justification of safe operation of reactor support components (RSC) are generally presented in the reports justifying RSC lifetime extension at Ukrainian NPPs. The experience of performing such calculations and analyzing the results indicates that there are issues to be improved.
V. Dubkovsky +3 more
openaire +2 more sources
HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS
Elektrotehnìka ta Elektroenergetika, 2018 Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical
S.V. Alyokhina
doaj +1 more source
Computer Assisted Methods in Engineering and Science, 2023 The paper presents selected results of the analysis of thermal and mass flow transient processes within the containments of the WWER-440 and the WWER-1000 nuclear reactors during Loss-of-Coolant Accidents based on the mathematical model and computer ...
Janusz Skorek, Jan Składzień
doaj
Control Valve Condition Checking by Spectral Analysis
Глобальная ядерная безопасность, 2022 The research work considers and analyzes the problem of control valve failure in case of shaft-gear break during normal operation. In order to identify typical deviations and causes of failure of the electrically driven valves, the amplitude-frequency ...
D. V. Shvets +3 more
doaj +1 more source