Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant-Reference-Cited by-同舟云学术

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Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant

Published:2024-07-12 Issue:29 Volume:63 Page:12927-12937
ISSN:0888-5885
Container-title:Industrial & Engineering Chemistry Research
language:en
Short-container-title:Ind. Eng. Chem. Res.

Author:

Fang Haofan¹^ORCID,He Mingjian¹^ORCID,Jiao Caishan¹^ORCID,Hou Chenxi¹^ORCID,Zhang Meng¹,Wang Jingyang¹

Affiliation:

1. College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150001, China

Funder

National Natural Science Foundation of China

Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment, Harbin Engineering University

Publisher

American Chemical Society (ACS)

Link

https://pubs.acs.org/doi/pdf/10.1021/acs.iecr.4c00983

Reference38 articles.

1. The development status of PUREX process for nuclear fuel reprocessing from an insight from PATENTS

2. Problems of modernization of spent nuclear fuel extraction processing

3. A Conceptual Process Study for Recovery of Uranium Alone from Spent Nuclear Fuel by Using High-Alkaline Carbonate Media

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