Microstructural and thermophysical properties of U–6wt.%Zr alloy for fast reactor application-Reference-Cited by-同舟云学术

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Microstructural and thermophysical properties of U–6wt.%Zr alloy for fast reactor application

Published:2012-08 Issue:1-3 Volume:427 Page:1-11
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kaity Santu,Banerjee Joydipta,Nair M.R.,Ravi K.,Dash Smruti,Kutty T.R.G.,Kumar Arun,Singh R.P.

Publisher

Elsevier BV

Subject

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

Reference46 articles.

1. History of fast reactor fuel development

2. A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design

3. Fuels for sodium-cooled fast reactors: US perspective

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1. Assay of zirconium and americium in the irradiated U-Zr metal alloy fuel slug;Journal of Nuclear Materials;2024-11

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4. Magnetism and finite-temperature effects in UZr2: A density functional theory analysis;Journal of Nuclear Materials;2024-07

5. Recovery and DFT investigation of Zr(IV) from U–Zr aqueous solutions by bisdiglycolamide ligand;Journal of Radioanalytical and Nuclear Chemistry;2024-05-10

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