Reactivity of Zircaloy-4 with Ti3SiC2 and Ti2AlC in the 1100–1300 °C temperature range-Reference-Cited by-同舟云学术

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Reactivity of Zircaloy-4 with Ti3SiC2 and Ti2AlC in the 1100–1300 °C temperature range

Published:2015-05 Issue: Volume:460 Page:122-129
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Tallman Darin J.,Yang Jian,Pan Limei,Anasori Babak,Barsoum Michel W.

Funder

DOE’s Office of Nuclear Energy University ProgramDOE’s Office of Nuclear Energy University Program (DOE/NEUP)

Publisher

Elsevier BV

Subject

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

Reference49 articles.

1. High temperature oxidation of zirconium and zircaloy-4 under applied load: Nuclear microprobe study of the growth of the oxide

2. Diffusion model for the oxidation of Zircaloy-4 at 400°C in steam. The influence of metallurgical structure (precipitates and grain size)

3. High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys

4. A review on the clad failure studies

5. Selection of fuel cladding material for nuclear fission reactors

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1. Microstructure evolution and degradation mechanisms of amorphous FeCrAlMoSiY coated Zr in 1200 °C steam;Vacuum;2024-11

2. Brazing Zircaloy-4 to Ti3AlC2 using Ti–Zr–Cu–Ni amorphous alloys: Microstructural evolution and mechanical properties;Materials Science and Engineering: A;2024-10

3. Fabrication of Al6061/Ti3AlC2 MAX phase surface composite by friction stir processing and investigation of wear properties;Tribology International;2024-07

4. Low-temperature direct diffusion bonding of Zr702 alloys via electric current assistance;Journal of Adhesion Science and Technology;2024-05-02

5. In-situ formation and barrier behavior of Zr2Si and ZrCrSi2 layers during the oxidation of Cr3Si coated Zry-4 at 1300 °C;Ceramics International;2024-05

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