Development of a New Aqueous Process for Nuclear Fuel Reprocessing: Hot Tests on the Recovery of U and Pu from a Nitric Acid Solution of Spent LWR Fuel-Reference-Cited by-同舟云学术

Development of a New Aqueous Process for Nuclear Fuel Reprocessing: Hot Tests on the Recovery of U and Pu from a Nitric Acid Solution of Spent LWR Fuel

Published:2005-02 Issue:2 Volume:149 Page:217-231
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wei Yuezhou¹,Arai Tsuyoshi¹,Hoshi Harutaka¹,Kumagai Mikio¹,Bruggeman Aimé²,Goethals Patrick²

Affiliation:

1. Institute of Research and Innovation Nuclear Chemistry and Chemical Engineering Center, 1201 Takada Kashiwa 277-0861, Japan

2. Belgian Nuclear Research Center (SCK/CEN), B-2400 Mol, Belgium

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT05-A3591

Reference29 articles.

1. Distribution of Various Elements between Nitric Acid and Anion Exchange Resin

2. Anion Exchange Characteristics of the Elements in Nitric Acid Medium.

3. The Application of an Advanced Ion Exchange Process to Reprocessing Spent Nuclear Fuels, (I)

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