Results 11 to 20 of about 34,801 (301)

Ab-initio calculations for structural properties of Zr-Nb alloys [PDF]

open access: yes, 2013
Ab-initio calculations for the structural properties of Zr-Nb alloys at different values of the niobium concentration are done at zero temperature. Different cases for Zr-Nb alloys with unit cells having BCC and HCP structures are considered.
Kharchenko, Dmitrii O.   +1 more
core   +5 more sources

Protection of AlCrNbSiTi High Entropy Alloy Coating on Zirconium Alloy by High-temperature Steam Oxidation at 1 200 ℃

open access: yesYuanzineng kexue jishu, 2023
It is one of the main ideas of developing ATF cladding materials to improve the accident resistance of zirconium alloy by coating. In the existing research on the protection mechanism of the coating on zirconium alloy substrate, the main focus is on the ...
TU Menghe;HU Yong;ZHANG Baoliang;LIU Xin;LI Shen;WANG Hui
doaj  

The influence of boron addition on properties of copper-zirconium alloys [PDF]

open access: yesScience of Sintering, 2023
Copper-zirconium alloys with high conductivity were produced using powder metallurgy. Two-steps manufacturing process, containing mechanical alloying followed by hot pressing, was applied in achieving improved mechanical and physical properties of Cu-Zr ...
Simić M.   +6 more
doaj   +1 more source

Capability assessment for application of clay mixture as barrier material for irradiated zirconium alloy structure elements long-term processing for storage during decommissioning of uranium-graphite nuclear reactors [PDF]

open access: yes, 2016
The radionuclide composition and the activity level of the irradiated zirconium alloy E110, the radionuclide immobilization strength and the retention properties of the mixed clay barrier material with respect to the radionuclides identified in the alloy
Kotlyarevskiy, S. G.   +3 more
core   +2 more sources

Study on Quantitative Method for Hydrogen Distribution in Zirconium Alloy via Neutron Tomography

open access: yesYuanzineng kexue jishu, 2023
Hydrogen ingress into zirconium cladding can cause embrittlement and affects the service safety of nuclear fuel cladding. Traditional hydrogen analysis methods like hydrogen determination instrument method and metallographic method, can only give the ...
WU Meimei;LIU Xin;HE Linfeng;HU Yong;RUAN Shihao;WANG Tianyun;LI Yuqing;WEI Guohai;SUN Kai
doaj  

FEM and Von Mises analysis on prosthetic crowns structural elements: evaluation of different applied materials [PDF]

open access: yes, 2017
The aim of this paper is to underline the mechanical properties of dental single crown prosthodontics materials in order to differentiate the possibility of using each material for typical clinical condition and masticatory load.
Cesare, D’Amico   +10 more
core   +1 more source

Effect of anodization on the surface characteristics and electrochemical behaviour of zirconium in artificial saliva [PDF]

open access: yes, 2016
The paper is focused on elaboration of ZrO2 films on pure zirconium via anodizing inphosphoric acid with and without fluoride at constant potentials of 30 V and 60 V.
Ceré, Silvia   +4 more
core   +1 more source

Investigations of Zr(IV) in LiF-CaF2: stability with oxide ions and electroreduction pathway on inert and reactive electrodes [PDF]

open access: yes, 2013
In this work, a detailed electrochemical study of the molten LiF-CaF2-ZrF4 system is provided in the 810-920°C temperature range, allowing the determination of the reduction potential, the diffusion coefficient and the reduction mechanism of dissolved Zr(
Cassayre, Laurent   +4 more
core   +4 more sources

Study on Growth Mechanism and Characteristics of Zirconium Alloy Micro-Arc Oxidation Film

open access: yesMetals, 2023
Ceramic coatings on R60705 zirconium alloy were prepared on the surface by the micro-arc oxidation (MAO) technique in electrolytes containing Na2SiO3, NaOH, and Na2EDTA.
Mingli Wang   +6 more
doaj   +1 more source

Effects of oxide layers on zirconium alloy-steam reaction

open access: yesJournal of Radiation Research and Applied Sciences, 2023
In a severe accident of a BWR plant, zirconium alloy of fuel cladding reacts with steam becoming a heat source for core melting and becoming a hydrogen source for hydrogen explosion.
Shunsuke Uchida   +3 more
doaj   +1 more source

Home - About - Disclaimer - Privacy