Lead and lead alloys. Lead and lead alloy sheaths and sleeves of electric cables

2003 ◽  
1999 ◽  
Vol 5 (S2) ◽  
pp. 918-919
Author(s):  
J.M. Vahaaho ◽  
P.A. Zieliński

Preparation of lead and lead alloy specimens for metallographic examination is more difficult than preparation of the majority of other metals and their alloys. The troublesome difference is that lead and lead alloys are soft (lead has a Vickers hardness of 4-5 [1,2]), and therefore readily develop a cold-worked surface layer and disturbances in the subsurface layers during mechanical polishing. The specimen softness also allows embedding of the abrasive particles. If not removed, these mechanically introduced artifacts obscure the true structure of the specimen, and in some cases could develop a pseudostructure, especially if excessive frictional heat is involved [1]. Usually etchpolishing, consisting of cycles of alternately etching, polishing, and microscopic examination, is required to remove the above artifacts. This treatment either might not completely remove these artifacts or it might overetch the sample. In addition, etching could introduce its own artifacts, such as tarnishing, etching pits, or both.


2011 ◽  
Vol 366 ◽  
pp. 181-186
Author(s):  
Jian Ping Li ◽  
Li Bang Zeng ◽  
Da Heng Mao ◽  
Hong Feng Jiang

With the ultrasound was put into the experiment of cast-rolling lead alloy strip, it broke the dendrite structures and enhanced the under-cooling by the effect of cavity and acoustic streaming. The microstructure comparison of ultrasound and general cast-rolling shows that: The grain size of general cast-rolled lead strip is big; the grain boundary is coarse and the organization structure is uneven. However, the grain structure is refined, smaller grains and uniform organization structure is acquired with ultrasound treatment. Besides, the mechanical properties test results of the two kinds lead alloys shows that the ultrasound cast-rolling lead alloys are better than general cast-rolling. The tensile strength, yield strength and elongation of ultrasound cast-rolling lead strip are increased by 11.30%, 22.15% and 21.74% than that of general cast-rolling lead strip.


1994 ◽  
Vol 29 (3) ◽  
pp. 193-200 ◽  
Author(s):  
H Fessler ◽  
T H Hyde

The objective of this paper is to show that there are model materials which can be used to develop better assumption to improve theories, to verify the applicability of theories, or to get creep information which is otherwise unobtainable. The mechanical properties necessary to characterize non-linear component behaviour are defined and presented for some chill-cast lead alloys at 20°C. When normalized, they are shown to be sufficiently similar to structural steels to allow the prediction of prototype response from model tests. This paper also describes the methods used to make lead alloy models for the experimental study of creep of components.


Author(s):  
Choonho Cho ◽  
Tae-Yung Song ◽  
Chungho Cho

A key problem in the development of heavy liquid metal cooled reactors is a corrosion of the structural and fuel cladding materials by the coolants. Thus, the problem has been considered as an important design-factor that limits the operational temperature and flow velocity of the next generation nuclear reactors using lead-alloys. Corrosion data has been obtained on as-received and active coating materials of HT9 and 316L in a stagnant lead-alloy containing a reduced atmosphere of oxygen with an exposure time of 1500 hours at 600°C. After each test, the specimens were analyzed metallurgically by using a scanning electron microscopy (SEM) with a energy dispersive X-ray analysis (EDX) for the cross sections of the specimens. In addition, X-ray diffraction (XRD) was performed to evaluate the phase composition of the steels.


2016 ◽  
Vol 8 (37) ◽  
pp. 6805-6814 ◽  
Author(s):  
J. Soares ◽  
M. A. G. Nunes ◽  
E. M. M. Flores ◽  
J. N. G. Paniz ◽  
V. L. Dressler

A method based on flow injection-hydride generation-inductively coupled plasma mass spectrometry (FI-HG-ICP-MS) for the determination of trace amounts of As, Bi, Sb, Se, Sn and Te in lead alloys was developed.


Author(s):  
Ryuta Hashidate ◽  
Takashi Onizawa ◽  
Takashi Wakai ◽  
Naoto Kasahara

Abstract This paper studies inelastic stress-strain relationship equation and creep rupture equation and creep strain equation of 99%lead-1% antimony alloy. Under the severe accident conditions, structural materials of nuclear power plants are subjected to excessive high temperature. Although it is very essential to clarify how the structure collapses under the severe accident conditions, there’re no experimental evidences of failure modes and the failure mechanisms in such high temperatures are not clarified. However, it is very difficult and expensive to perform structural tests using actual structural materials, such as austenitic stainless steels. Therefore, the authors propose to use lead alloys instead of actual structural materials. Because the strength of such alloys is much poorer than that of the actual structural materials, failure can be observed at much low temperature and by much small load. For demonstration of analogy between the failure mechanisms of lead alloy structure at low temperature and those of the actual structures at extremely elevated temperature, numerical analyses are required. The authors proposes inelastic constitutive equations of lead alloy based on a series of material tests. Nonlinear numerical analyses, e.g. finite element analyses, can be performed using the proposed equations.


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