Determination of six trace elements in zirconium alloy by cation exchange resin chromatography and inductively coupled plasma atomic emission spectrometry;

Determination of Trace Impurity Elements in Zirconium Alloy by ICP-AES;

Determination of micro hafnium in zirconium alloy by inductively coupled plasma-atomic emission spectrometry;

Study on the effect of texture on tension and burst properties of zirconium alloys;

The recent progress of R&D and manufacture Scenario for zirconium alloys as structural materials in the core of nuclear reactor in China is reviewed in this paper.

Some surface treatment processes of zirconium alloys were introduced.

So the nanocrystalline treatment leads to fine grain of ZrO2 and has influence on the oxidation dynamics of zircaloy-

In this paper a computation model of corrosion rate versus grain size of nanocrystalline zircaloy-4 has been presented.

In this paper, research results and disadvantages of main bonding process of zircaloy and stainless steel are reviewed.

As a light water nuclear reactor fuel cladding material,Zr alloy has been wide used and its application experience accumulated,hence it is the potential materials for SCWR.

Based on the analysis of welding properties of zirconium and zirconium alloys,and through the welding test and research,the zirconium and zirconium alloy piping welding process has been obtained and summarized,and the welding technical specification was also stipulated.