Influence of precipitate density on the nodular corrosion resistance of Zr–Sn–Fe–Cr alloys at 500°C-Reference-Cited by-同舟云学术

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Influence of precipitate density on the nodular corrosion resistance of Zr–Sn–Fe–Cr alloys at 500°C

Published:2001-02 Issue:2-3 Volume:288 Page:237-240
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Charquet D.

Publisher

Elsevier BV

Subject

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

Reference10 articles.

1. H.G. Weidinger, F. Garzarolli, C.M. Eucken, E.F. Baroch, in: Zirconium in the Nuclear Industry, ASTM–STP 939, 1987, p. 364

2. F. Garzarolli, H. Stehle, in: Improvements in Water Reactor Fuel Technology and Utilization, IAEA, Vienna, 1987, p. 387

3. T. Andersson, T. Thorvaldsson, in: Zirconium in the Nuclear Industry, ASTM–STP 939, 1987, p. 321

4. B. Cheng, R.B. Adamson, in: Zirconium in the Nuclear Industry, ASTM–STP 939, 1987, p. 387

5. P. Rudling, G. Wikmark, B. Lehtinen, H. Petterson, in: ASTM–STP 1354, 2000, p. 678

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2. Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review;Frontiers in Materials;2024-04-16

3. Effect of oxygen content in 400 ℃ super-heated steam on the corrosion resistance of Zr-xSn-0.35Fe-0.15Cr-0.15 Nb alloys;Corrosion Science;2022-04

4. The influence of microtexture on the formation mechanism of nodules in Zircaloy-4 alloy tube;Journal of Materials Science & Technology;2020-06

5. Corrosion behaviors of Zr-Sn-Nb-Fe-Mo alloys in pure water at 360 °C/18.6 MPa: Influence of annealing temperature on the anti-corrosion properties;Corrosion Science;2020-02

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