Published 2014 | Version v1
Book

Estimation of boron in sodium borosilicate glass frit by fusion at lower temperature

  • 1. Tarapur Waste Management Plant, Nuclear Recycle Board, Bhabha Atomic Research Centre, Tarapur (India)

Description

In India High level radioactive liquid waste is immobilized in sodium borosilicate glass matrix. Chemical characterisation of the glass frit is essential to decide the waste to glass frit ratio for vitrification operation. Dissolution of glass sample for its characterization is done by fusion with Sodium carbonate at high temperatures. The error in the estimation of Boron in this fused glass is high due to volatalisation of boron at high temperature. Present paper details the use of sodium hydroxide as flux for fusion of glass sample at lower temperature. The boron is estimated by alkalimetric titration in presence of glycols like glycerol. The effect of presence of other glass components was also studied. Estimation of only boric acid with out fusion has shown recovery of 99.0 %. The boron recovery after fusion with NaOH pellets was found to be 97 - 98 %. The recovery of boron in presence of glass components like Fe2O3, TiO2 and SiO2 together has indicated recovery of about 97-98 %. Further for the sodium borosilicate glass samples the recovery obtained is 92-94%. The lower value is due to the volatilization of boron during glass preparation. (author)

Part of:
Proceedings of the DAE-BRNS fifth symposium on nuclear analytical chemistry

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the DAE-BRNS fifth symposium on nuclear analytical chemistry
Imprint Pagination
603 p.
Journal Page Range
p. 274-275

Conference

Title
5. DAE-BRNS symposium on nuclear analytical chemistry
Acronym
NAC-V
Dates
20-24 Jan 2014
Place
Mumbai (India)

Optional Information

Notes
5 refs., 2 tabs.