Journal of Radioanalytical and Nuclear Chemistry
Volume/Issue:
Volume 292: Issue 2
Preparation of uranium oxide powder for nuclear fuel pellet fabrication with uranium peroxide recovered from uranium oxide scraps by using a carbonate–hydrogen peroxide solution
Authors:
Kwang-Wook Kim Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Jae-Won Lee Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Dong-Young Chung Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Eil-Hee Lee Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Kweon-Ho Kang Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Kune-Woo Lee Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Kee-Chan Song Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Myung-June Yoo KEPCO NF, 1047 Daedeok daero, Yuseong, Daejeon, 305-353 Republic of Korea

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Geun-Il Park Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Jei-Kwon Moon Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 Republic of Korea

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Pages:
909–916
Online Publication Date:
05 Apr 2012
Publication Date:
01 May 2012
Article Category:
Research Article
DOI:
https://doi.org/10.1007/s10967-011-1534-8
Keywords:
Uranium scrap; Uranium peroxide; Carbonate; Hydrogen peroxide; Fuel pellet; Sinterability; OREOX
Restricted access

Abstract  

This work studied a way to reclaim uranium from contaminated UO2 oxide scraps as a sinterable UO2 powder for UO2 fuel pellet fabrication, which included a dissolution of the uranium oxide scraps in a carbonate solution with hydrogen peroxide and a UO4 precipitation step. Dissolution characteristics of reduced and oxidized uranium oxides were evaluated in a carbonate solution with hydrogen peroxide, and the UO4 precipitation were confirmed by acidification of uranyl peroxo–carbonate complex solution. An agglomerated UO4 powder obtained by the dissolution and precipitation of uranium in the carbonate solution could not be pulverized into fine UO2 powder by the OREOX process, because of submicron-sized individual UO4 particles forming the agglomerated UO4 precipitate. The UO2 powder prepared from the UO4 precipitate could meet the UO2 powder specifications for UO2 fuel pellet fabrication by a series of steps such as dehydration of UO4 precipitate, reduction, and milling. The sinterability of the reclaimed UO2 powder for fuel pellet fabrication was improved by adding virgin UO2 powder in the reclaimed UO2 powder. A process to reclaim the contaminated uranium scraps as UO2 fuel powder using a carbonate solution was finally suggested.

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Cover Journal of Radioanalytical and Nuclear Chemistry
Journal of Radioanalytical and Nuclear Chemistry
Print ISSN:
0236-5731
Online ISSN:
1588-2780

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Journal of Radionalytical and Nuclear Chemistry
Language English
Size A4
Year of
Foundation		 1968
Volumes
per Year		 1
Issues
per Year		 12
Founder Akadémiai Kiadó
Founder's
Address		 H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
Publisher Akadémiai Kiadó
Springer Nature Switzerland AG
Publisher's
Address		 H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
CH-6330 Cham, Switzerland Gewerbestrasse 11.
Responsible
Publisher		 Chief Executive Officer, Akadémiai Kiadó
ISSN 0236-5731 (Print)
ISSN 1588-2780 (Online)

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