Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment. [PDF]
Materials (Basel), 2023 Margolin B +5 more
europepmc +1 more source
Simulation of reactor transients in vver-1000 for pretraining of operating personnel
Известия высших учебных заведений: Проблемы энергетики, 2017 The pretraining system for NPP operating personnel in WWER-1000 is proposed. The basis of this system is computer simulation of reactor transients. The software packages and procedural guides for mathematical simulation of nuclear reactor kinetics are ...
M. A. Volman
doaj +1 more source
Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]
Materials (Basel), 2022 Zhou L +6 more
europepmc +1 more source
Estimation of the error of functionals calculation results of the neutron flux onto the WWER 1000 reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2012 It is shown that systematic calculation errors of functionals of the neutron flux onto WWER 1000 reactor pressure vessel are pseudorandom. The error of the neutron flux functionals is estimated on the basis of this fact and the data obtained with the ...
V. L. Diemokhin +2 more
doaj
Statistical Characterization of Strain-Controlled Low-Cycle Fatigue Behavior of Structural Steels and Aluminium Material. [PDF]
Materials (Basel), 2022 Bazaras Ž, Lukoševičius V.
europepmc +1 more source
Effect of Fuel Burnup History on Neutronic Characteristics of WWER-1000 Core
Nuclear and Radiation Safety, 2014 In preparation of few-group cross-section libraries to be used in WWER macro-calculations, change in the nuclide composition during fuel burnup is commonly defined under invariable characteristics, averaged over the entire core (power, fuel and moderator temperature, moderator density etc.).
Yu. Bilodid +4 more
openaire +3 more sources
Improvement of operational effectiveness criteria of WWER-1000 fuel loading
Nuclear Physics and Atomic Energy, 2002 Based on the examples of typical fuel cycles of WWER-1000 reactor the approaches and criteria allowing to perform the evaluation of effectiveness are considered. Particular attention is focused on the fact that during the operation of fuel loading the average level of reactor heat power is lower to nominal.
A.A. Korennoj, N.A. Fridman
openaire +1 more source
Comparison of radiation hazard of HLW in several spent nuclear fuel reprocessing scenarios
EPJ Web of Conferences, 2012 Radiation hazard of radionuclide has been calculated as a product of Aε where A is an activity of radionuclide and ε is a dose coefficient through ingestion. The values Aε of 18 radionuclide in spent fuel of WWER-440 are calculated.
Gladilov D., Ochkin A., Stefanovsky S.
doaj +1 more source
Application of Probabilistic Leak-Before-Break for WWER-1000 Unit
Procedia Structural Integrity, 2019 Abstract In this paper a probabilistic Leak-Before-Break analysis for WWER-1000 unit was performed based on the Failure Assessment Diagram (FAD), treating strength and crack morphology parameters as stochastic values. In order to perform probabilistic calculations Critical temperature of brittleness and Yield (Ultimate) Stress, were fitted by normal ...
openaire +1 more source
Analysis of Cation Resins for WWER-1000 Reactor Coolant Purification Filters
Energy Engineering and Control SystemsThe paper considers filtration equipment used for coolant purification in WWER-1000 reactors, which plays an important role in providing an optimal water-chemical regime, reducing radioactive contamination of equipment and extending the service life of ...
Halyna Matiko, Nazar Zosymchuk
doaj +1 more source