scholarly journals STUDIES ON THE U--Pu--Zr ALLOY SYSTEM FOR FAST BREEDER REACTOR APPLICATIONS.

1970 ◽  
Author(s):  
D.R. Harbur ◽  
J.W. Anderson ◽  
W.J. Maraman
Keyword(s):  
Alloy System ◽  
Fast Breeder Reactor ◽  
Zr Alloy

scholarly journals Effect of Cd and SPD on structure, physical, mechanical, and operational properties of alloy of Cu-Cr-Zr

2020 ◽  
Vol 59 (1) ◽  
pp. 506-513
Author(s):  
Denis A. Aksenov ◽  
Georgiy I. Raab ◽  
Rashid N. Asfandiyarov ◽  
Vladimir I. Semenov ◽  
Lev Sh. Shuster
Keyword(s):  
Wear Resistance ◽  
Structure Refinement ◽  
Alloy System ◽  
Environmental Safety ◽  
Structural Refinement ◽  
Industrial Systems ◽  
Ultrafine Grained ◽  
Positive Effect ◽  
Complete Processing ◽  
Zr Alloy

AbstractAn increase in the service life of electrical products from copper and its alloys is directly related to an increase in the wear resistance of materials. Structural refinement and alloying with cadmium are known to have a positive effect on the strength characteristics and wear resistance of copper, which makes it possible, with a Cd content of 1% by weight, to increase the wear resistance of copper several times, but cadmium is considered an environmentally unsafe element. In this regard, the paper presents the results of studies of a widely used Cu-Cr-Zr alloy system in the ultrafine-grained (UFG) state, micro-alloyed with cadmium (0.2%, weight), in order to improve physical, mechanical, and operational properties, as well as environmental safety. Severe plastic deformation, providing structure refinement to ~150 nm, and microalloying with cadmium of a Cu-Cr-Zr system alloy, after a complete processing cycle, provides a tensile strength of 570±10 MPa and 67% electrical conductivity. At the same time, the abrasion resistance increases by 12 and 35% relative to the industrial systems Cu-Cd and Cu-Cr-Zr, respectively. The obtained characteristics are very promising for improving the operational properties of continuous welding tips, collector plates, and contact wires operating under conditions of intense wear.

Formation of amorphous phase in the binary Cu−Zr alloy system

2006 ◽  
Vol 12 (3) ◽  
pp. 207-212 ◽  
Author(s):  
O. J. Kwon ◽  
Y. C. Kim ◽  
K. B. Kim ◽  
Y. K. Lee ◽  
E. Fleury
Keyword(s):  
Amorphous Phase ◽  
Alloy System ◽  
Zr Alloy

Quaternary and Quinary Ni-based Amorphous Alloys in the Ni-Zr-Ti-X (X=Al, Si, P) and Ni-Zr-Ti-Si-Y (Y=Sn, Mo, Y) Systems

2000 ◽  
Vol 644 ◽  
Author(s):  
M.H. Lee ◽  
S. Yi ◽  
T.G. Park ◽  
W.T. Kim ◽  
D.H. Kim
Keyword(s):  
Amorphous Alloys ◽  
Alloy System ◽  
Continuous Heating ◽  
Liquid Region ◽  
Undercooled Liquid ◽  
Bulk Amorphous Alloys ◽  
Glass Forming ◽  
Structural Application ◽  
Crystallization Mode ◽  
Zr Alloy

AbstractNew Ni-based bulk amorphous alloys in the alloy system Ni-Zr-Ti-X (X=Al, Si, P) and Ni-Zr- Ti-Si-Y (Y=Sn, Mo, Y) were developed through systematic alloy design based upon the empirical rules for high glass forming ability (GFA). Additions of a small amount of Si and/or Sn to a ternary Ni-Ti-Zr alloy are very effective to increase GFA as well as the undercooled liquid region (ΔTX). Changes in crystallization mode during continuous heating of amorphous phase and lowered liquidus temperature by quaternary and quinary additions are associated with the enhanced GFA and the enlarged ΔTx. Development of new Ni-based amorphous alloys with high GFA and large ΔTx expands structural application of amorphous alloys.

scholarly journals Interaction studies between U-Zr alloy system and ceramic plasma-spray coated layer at elevated temperature

2018 ◽  
Vol 5 (0) ◽  
pp. 192-195
Author(s):  
Ki-Hwan Kim ◽  
Ki-Won Hong ◽  
Hoon Song ◽  
Seok-Jin Oh ◽  
Jeong-Yong Park
Keyword(s):  
Elevated Temperature ◽  
Plasma Spray ◽  
Alloy System ◽  
Interaction Studies ◽  
Coated Layer ◽  
Zr Alloy

Evaluation of glass forming ability in the Ni–Nb–Zr alloy system by the topological instability (λ) criterion

2010 ◽  
Vol 495 (2) ◽  
pp. 313-315 ◽  
Author(s):  
F.S. Santos ◽  
C.S. Kiminami ◽  
C. Bolfarini ◽  
M.F. de Oliveira ◽  
W.J. Botta
Keyword(s):  
Alloy System ◽  
Glass Forming Ability ◽  
Glass Forming ◽  
Zr Alloy

scholarly journals Electron correlation and relativity of the 5f electrons in the U–Zr alloy system

2014 ◽  
Vol 444 (1-3) ◽  
pp. 356-358 ◽  
Author(s):  
P. Söderlind ◽  
B. Sadigh ◽  
V. Lordi ◽  
A. Landa ◽  
P.E.A. Turchi
Keyword(s):  
Electron Correlation ◽  
Alloy System ◽  
5F Electrons ◽  
Zr Alloy

scholarly journals Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

2021 ◽  
Vol 11 (3) ◽  
pp. 1308
Author(s):  
Hui Zhao ◽  
Chong Yang ◽  
Dongxu Guo ◽  
Lu Wu ◽  
Jianjun Mao ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Neutron Radiation ◽  
Alloy System ◽  
Thermomechanical Coupling ◽  
Fuel Cladding ◽  
Coupling Behavior ◽  
Long Time ◽  
User Material Subroutine ◽  
Fuel Elements ◽  
Zr Alloy

Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors. Usually, it is in service for a long time under the effects of neutron radiation with high temperature and high pressure, which results in thermomechanical coupling behavior during the service process. Focusing on the UO2/Zr fuel elements, the macroscopic thermomechanical coupling responses of pure Zr, Zr-Sn, and Zr-Nb binary system alloys, as well as Zr-Sn-Nb ternary system alloy as cladding materials, were studied under neutron irradiation. As a heat source, the thermal conductivity and thermal expansion coefficient models of the UO2 core were established, and an irradiation growth model of a pure Zr and Zr alloy multisystem was built. Based on the user material subroutine (UMAT) with ABAQUS, the current theoretical model was implemented into the finite element framework, and the consequent thermomechanical coupling behavior under irradiation was calculated. The distribution of temperature, the stress field of the fuel cladding, and their evolution over time were analyzed. It was found that the stress and displacement of the cladding were sensitive to alloying elements due to irradiated growth.

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