Wet chemical processing for nuclear waste glass to retrieve radionuclides.

Acid leaching Long-lived fission products Nuclear waste glass Retrieval Vitrification

Journal

Journal of hazardous materials
ISSN: 1873-3336
Titre abrégé: J Hazard Mater
Pays: Netherlands
ID NLM: 9422688

Informations de publication

Date de publication:
15 Jan 2019
Historique:
received: 26 06 2018
revised: 24 08 2018
accepted: 12 09 2018
pubmed: 25 9 2018
medline: 25 9 2018
entrez: 25 9 2018
Statut: ppublish

Résumé

Here, we show unexpected and significant elution behavior of various elements from simulated nuclear waste glass (NWG) in ∼10° mol dm

Identifiants

pubmed: 30245404
pii: S0304-3894(18)30837-9
doi: 10.1016/j.jhazmat.2018.09.042
pii:
doi:

Types de publication

Journal Article

Langues

eng

Pagination

368-374

Informations de copyright

Copyright © 2018 Elsevier B.V. All rights reserved.

Auteurs

Koichiro Takao (K)

Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, 2-12-1 N1-32, O-okayama, Meguro-ku, 152-8550 Tokyo, Japan. Electronic address: ktakao@lane.iir.titech.ac.jp.

Takahiro Mori (T)

Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, 2-12-1 N1-32, O-okayama, Meguro-ku, 152-8550 Tokyo, Japan.

Mayuu Kubo (M)

Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, 2-12-1 N1-32, O-okayama, Meguro-ku, 152-8550 Tokyo, Japan.

Akihiro Uehara (A)

Research Reactor Institute, Kyoto University, 2, Asashiro-Nishi, Kumatori-cho, Sennan-gun, 590-0494 Osaka, Japan.

Yasuhisa Ikeda (Y)

Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, 2-12-1 N1-32, O-okayama, Meguro-ku, 152-8550 Tokyo, Japan.

Classifications MeSH