Synthesis, Characterization and Dissolution behavior of Nitrides of U-Zr and U-Pu-Zr metallic alloy fuels for Aqueous reprocessing-Reference-Cited by-同舟云学术

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Synthesis, Characterization and Dissolution behavior of Nitrides of U-Zr and U-Pu-Zr metallic alloy fuels for Aqueous reprocessing

Published:2024-08 Issue: Volume:596 Page:155106
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Bootharajan M.^ORCID,Sreenivasulu B.,Murthy A. Sree Rama^ORCID,Jain Ashish^ORCID,Sundararajan K.^ORCID,Rao C.V.S. Brahmananda,Jayaraman V.,Sivaraman N.

Publisher

Elsevier BV

Reference46 articles.

1. Development of pyroprocessing technology;Laidler;Prog. Nucl. Energy.,1997

2. Irradiation behavior of metallic fast reactor fuels;Pahl;J. Nucl. Mater.,1992

3. Metallic fast reactor fuels;Hofman;Prog. Nucl. Energy.,1997

4. 12-Reprocessing and recycling;DelCul,2020

5. Oxidation and dissolution behavior of UZr alloys for aqueous reprocessing applications;Sreenivasulu;Prog. Nucl. Energy.,2022

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

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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