Determination of Fe and Cr content in α-Zr solid solution of Zircaloy-4 with different heat-treated states

Author:

Li Cong,Zhou Bangxin,Zhou Wenjin,Li Pei,Peng Qian,Ying Shihao,Shen Baoluo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference18 articles.

1. F. Garzarolli et al., IAEA STI/PUB/721, International Atomic Energy Agency, Vienna, 1987, p. 387

2. G. Garzarolli et al., Zirconium in the nuclear industry, in: Eighth International Symposium, ASTM STP 1023, American Society for Testing and Materials, Philadelphia, 1989, p. 202

3. P. Rudling et al., Zirconium in the nuclear industry, in: Tenth International Symposium, ASTM STP 1245, American Society for Testing and Materials, Philadelphia, 1994, p. 599

4. A unified model of Zircaloy BWR corrosion and hydriding mechanisms

5. D. Charquet, Zirconium in the nuclear industry, in: Twelfth International Symposium, ASTM STP 1354, American Society for Testing and Materials, West Conshohocken, PA, 2000, p. 3

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