Results 81 to 90 of about 648 (179)

Analysis of calculation of fuel rods for strength under transient and steady-state operating conditions

open access: yesNuclear Materials and Energy
The operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
doaj   +1 more source

ICONE15-10327 VVER SAFETY ANALYSIS BY THE COUPLED CODE ATHLET/BIPR-VVER

open access: yesThe Proceedings of the International Conference on Nuclear Engineering (ICONE), 2007
Nikonov, S.   +4 more
openaire   +1 more source

An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly

open access: yesЯдерна фізика та енергетика, 2016
Considering the fuel assembly (FA) load history and the nonuniformity of energy release for the fuel elements (FEs) contained in this FA, a method for forecasting of probability of VVER-1000 FE cladding failure due to FE cladding deformation damage ...
S. N. Pelykh   +2 more
doaj  

Evolution of dislocation microstructure in irradiated Zr alloys determined by X-ray peak profile analysis. [PDF]

open access: yesJ Appl Crystallogr, 2021
Groma I   +7 more
europepmc   +1 more source

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

open access: yesMaterials (Basel), 2022
Zhou L   +6 more
europepmc   +1 more source

Study of the Influence of Thermomechanical Treatment on the Structure and Properties of Zircalloy-4 Alloy. [PDF]

open access: yesMaterials (Basel)
Popov F   +6 more
europepmc   +1 more source

Home - About - Disclaimer - Privacy