Extraction Behavior of Fission Products with Tri-n-butyl Phosphate by Countercurrent Multistage Extraction in a Uranium, Plutonium, and Neptunium Co-recovery System-Reference-Cited by-同舟云学术

Extraction Behavior of Fission Products with Tri-n-butyl Phosphate by Countercurrent Multistage Extraction in a Uranium, Plutonium, and Neptunium Co-recovery System

Published:2012-09-26 Issue:40 Volume:51 Page:13245-13250
ISSN:0888-5885
Container-title:Industrial & Engineering Chemistry Research
language:en
Short-container-title:Ind. Eng. Chem. Res.

Author:

Nakahara Masaumi¹,Nakajima Yasuo¹,Koizumi Tsutomu¹

Affiliation:

1. Nuclear Fuel Cycle Engineering Laboratories and ‡Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194, Japan

Publisher

American Chemical Society (ACS)

Subject

Industrial and Manufacturing Engineering,General Chemical Engineering,General Chemistry

Link

https://pubs.acs.org/doi/pdf/10.1021/ie3011287

Reference8 articles.

1. Koyama, T., Washiya, T., Nakabayashi, H., and Funasaka, H.Current status on reprocessing technology of fast reactor fuel cycle technology development (FaCT) project in Japan–Overview of reprocessing technology development.Proceedings of the International Conference on the Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives (GLOBAL 2009),Paris, France, September 6–11, 2009; paper9100.

2. Extraction en milieu nitrique du thorium, du neptunium, du plutonium, par les solutions de phosphate de tributyle chargees en uranium

3. Oxydation du neptunium(V) par les solutions aqueuses d'acide nitrique en presence d'acide nitreux

4. Separation of Actinide Elements by Solvent Extraction Using Centrifugal Contactors in the NEXT Process

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