Oxidation and dissolution behavior of UZr alloys for aqueous reprocessing applications

Author:

Sreenivasulu B.ORCID,Parida Sanjit Kumar,Chandran K.,Sriram S.,Jena Hrudananda,Rao C.V.S. Brahmananda,Suresh A.,Jayaraman V.,Sivaraman N.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference24 articles.

1. Oxidation of uranium alloys in carbon dioxide and air;Antill;J. Less Common. Met.,1961

2. Buck Research Cr-1a User's Manual;Buck,1996

3. Christian J.D., Aqueous Reprocessing of U-Pu-Zr Metal Fuels – Dissolution Considerations. vol. 3122 Homestead Lane: Idaho Falls, ID, 83404.

4. Dissolution behaviour of simulated MOX nuclear fuel pellets in nitric acid medium;Desigan;Prog. Nucl. Energy,2019

5. The Dissolution of Zirconium-Clad Uranium Target Elements. No. LRL-73;Gercke,1953

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