Published May 2017 | Version v1
Miscellaneous

Aluminium oxide grafted kaolinite for efficient uranium removal from aqueous solution

  • 1. Nuclear Materials Authority, Cairo (Egypt)

Description

Due to extensive diversity of nuclear applications, efficient adsorbents are highly required for radioactive liquid waste treatment. In this investigation, costless and simple approach for removing uranium from liquid waste by aluminum oxide grafted kaolinite (AOGK) was stated. The influences of contact time, solution pH, initial uranium concentration, adsorption temperature, adsorbent amount (dose) on the adsorption of uranium (VI) ions from radioactive liquid waste were investigated. The theoretical capacity of AOGK adsorbent is about 95 mg/g AOGK. The optimum adsorption conditions were recommended. About 95% of the loaded Uranium (VI) on AOGK adsorbent has been eluted by ascorbic acid as an efficient eluent.

Part of:
ALTA 2010 Uranium-REE Conference: 13th Uranium Event

Additional details

Publishing Information

ISBN
978-0-9925094-9-1
Imprint Title
ALTA 2017 Uranium-REE Conference: 13th Uranium Event
Imprint Pagination
322 p.
Journal Page Range
p. 300-314

Conference

Title
13. Uranium-REE Conference
Acronym
ALTA 2017
Dates
25-26 May 2017
Place
Perth, WA (Australia)

Optional Information

Notes
14 figs., 4 tabs., 45 refs. Imprint:Includes Lithium Processing Forum