Estimation of the contribution of radiation-induced dislocation loops and precipitates to radiation hardening of rpv metal of reactors WWER-440 and WWER-1000 [PDF]
, 2013 Для корпусного металла (основной металл и металл сварного шва) реакторов типа ВВЭР-440 и ВВЭР- 1000 разделен вклад в общее радиационное упрочнение двух его составляющих, а именно: упрочнения, создаваемого радиационно-индуцированными дислокационными ...
Дубинко, В.И. +5 more
core +1 more source
Simulation of error in suppression of Xenon oscillations in a WWER-1000 nuclear reactor
, 2018 Errors in suppression of xenon oscillations refer to anticipated operational occurrences. Such errors could be treated as a long-term absence of some special actions used to stabilize the power field or incorrect movements of the control and protection ...
R. Akbari +2 more
core +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
Weiterfuehrung und Abschluss der Verifizierung von Rechenprogrammen fuer WWER-1000 Abschlussbericht
, 1993 The plans for backfitting the WWER-440 and WWER-1000 reactors still in operation must be prepared on the basis of thorough safety analyses. The project reported was to establish an integrated verification of the tools for computation of the physics ...
Rebohm, H. +7 more
core
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