Results 61 to 70 of about 127,616,970 (139)

Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant-Experiments and Modeling. [PDF]

Materials (Basel), 2023
Betova I, Bojinov M, Karastoyanov V.
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, V. V. Ilkovich, V. M. Bukanov   +2 more
doaj  

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment. [PDF]

Materials (Basel), 2023
Margolin B, Pirogova N, Sorokin A, Kokhonov V, Dub A, Safonov I.   +5 more
europepmc   +1 more source

Evolution of WWER-1000 Designs

, 2011
Описана эволюция проектов реакторных установок с ВВЭР-1000 различных модификаций. Рассмотрены отличия, внесенные в проекты реакторных установок нового поколения с целью повышения безопасности и надежности.
Стефанишин, Н.А., Колтаков, В.И., Остапчук, С.А.   +2 more
core  

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

Improved determination of fast neutron fluence onto the WWER pressure vessel metal surveillance specimens [PDF]

EPJ Web of Conferences
The special methodology for the determination of the neutron fluences onto the surveillance specimens of the WWER-1000 reactor pressure vessel metal has developed by INR NASU specialists and is successfully applied.
Pugach O.M., Bukanov V.M., Diemokhin V.L., Grytsenko O.V., Vasylieva O.G.   +4 more
doaj   +1 more source

Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]

Materials (Basel), 2022
Zhou L, Dai J, Li Y, Dai X, Xie C, Li L, Chen L.   +6 more
europepmc   +1 more source

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

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., Schulz, G., Maier, A., Becker, R., Thomas, S., Kraftwerks- und Anlagenbau AG (KAB), Berlin (Germany), Moeller, W., Krell, J.   +7 more
core  

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, A. Kuchin, V. Khalimonchuk, M. Yeremenko, Yu. Ovdiienko   +4 more
openaire   +3 more sources